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Wisconsin-Electric PowR coMPANY 231 el MICHIGAN. P.O. BOX V46. MIL',%AUXEE. W, 53201

Septer-ber 16, 1981

Mr. Earold R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUC-LzPAR REGULATORY COM.LISSION Washington, D. C. 20555

Attention:

Gentlemenz

Mr. R. A. Clark, Chief Operating Reactors Branch 3

DOCKET I0S. 50-266 AND 50-301 ADDITIONAL Ik1'FOFdJ'TION

JA.UXILIARY . . .TER SYST-V{ -POIN"-' BEACh NUCLEAR 0ATr.Nf UNITS 1 AND 2

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On July 30 we received your letter dated Jurly 28, 1981, requesting additional information concerning automatic init-iation. of the auxiliary feedwater (.AFW) system and flow indication for the AFW system at the Point Beach Nuclear Plant. You will note that some of the information you have requested has been prevoualy provided to the NRC. ThereforQ, in several of the following responses we have referenced previous submittals.

The specific information requested and our response iz as follows:

1. Is the auxiliary feedwater system and its automatic initiation circuitry conslidered to be part of the Engineered Safety Featursio (ESF)?

RESPONSE: Chapter Six of the Point Beach Nuclear Plant Final Facility Description ard Safety Analysis Report (FFDSAR) describes the ES.F --ystems included in ý.he Point Beach 1;uclear Plant design. The kFli system is not listed among these systers. However, as stated several times in our previous fiL_.s, including cur, December 31, 1979 NUREG-0578 letter at Item 2.1.7.a, the Point. Beach

•aFW oyltem is a s fety-grde.3ys-t e ,ihich provides for automatic initiation a-d i. dj-1,,od to -- e sincJe-failure criteria. Tcabi_. of t. 2igna].s and circait3 exi<st, essentially to the dearer as for other -afuty--,-rad,- . "•, .- r .... consider the AFW system to be cciva>~nt to specifically listed as ESFv. in th-2 -F-'.S."-Z..

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2. Are there any operating bypasses associated with the automatic initiation logic/circuitry during startu. or operation of the react-or? If no, how are thes.bypasses removed (autor'.-.tically, procedurally, etc.)?

RESPONtE: During plant startup, the control room sw-ee for the main feedwater pu=p2 are mainta. in a 'pull-outI conc.-.ion. While the main feedwater pump switches are in this condition, autcmatic sta't of th.e motor-driven AFW pumps on only the a.asociated unit ia precluded. In the early stages of a unit ztartup, the motor-driven AFW pumps are usc-d to .cntrol steam generator level. Steam generator feed is shifte.d "ho the :iain feedwater pu-ps by procedural otep prior to latching the main turbine.

Once steam generator feed is shifted to the maln leadwater pumps, bypass of the APW auto.matic initiation signal is eliminated. There are no other operat.ing bypasses azsociated with automati.- AU-W actaation. It should be noted that placing the nJ - feedwater ?"= contrcl switches in *pull.-out".doe: c affect tha automa.tic actuation of the ste=m-d--ven AF-W pumps in either utit.

3. Describe the st.& generator level 1nstru-entation at Point Beach 3. and 2. Ths descriptic should include:

a) Type and number of level channels Ver zte,-m generator including th.E range of each channel.

b) The specific source (vital bus) from which each of thene channels is powered.

c) Capability for testing and calibration including interval between tests.

d) The apecific indication available in ti-e control room for each channel.

RLSPONSE: The nuraber of steam generator level channels and the specific power source for each of these chanlnels was previously provided to the NRC at item 2.1.7.b of our March 14, 1980 letter on NUPEG-057S im=pl--.entatiOn. Each of the th-ee steam generator !avcl channels ccnsists of a differentiaJ.l pre-su transmit-c outputing a level

AA proporr±oinal 10-50 =-a current Lo 1the •-,-oteCt-iCn, and indIcaticn devices nsseciated ,ith L 0.1"h 2. e C -f 7 _2 a c h c *:1 :," .. .. .. . i s, 0 i- Wa 0"_ ý ov e r_I•. - .1 3. • ,, c z -w a t e r l ede l t h. Z ý 2=,.• z e o ra,- -n • i ' ' - C%,) 3 7 "12 ,h c

of actu n. tc stea qenC_=:tzC- level. , ,-:-,.'':q- ;.•'

Mr. Harold R. Denton -2- September i15, 1981

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Mr. Harold R. Denton -3- September 16, 1981

generator level indication is also provided but does not input control, protection or actuation circuitry.) The testing and calibration requireiaents for the steam generator level channels- are specified in the plant Technical Specifications at item 11 of Table 15.4.1-I. Control room indication for each of the steam generetor level channels consists of a separate analog meter for •ach chanznel with a range of 0-100%.

4. Describe the AFW flow channels %t Point Beach. This description should include:

a) The specific source (vital bue) from which each channel is powered.

b) Capability for testing and calibration including interval between tests. Indicate whether this testing is requirad by the Point Beach Units I and 2 5.echnical Specifications.

c) The specific indication available in the cDntroi room for each channel.

RESPONSEZ The Pclnt Beach Nuclear Plant Wow has two revel of alrect AFW floow indicatioz-avnllable in the control room. AFW pump discharq.a flow-indication is available for each pump. This flow channel was described in actail at Item 2.1..7 h of our march 14, 1980 letter. A schematic of these channels, including the specific power sources, was provided with our December 31;- 1979 letter. WQ have also recently completed the installation of flow indicators for AYW flow to each steam generator. These channels consist of four flow transmitters, one for each steam generator, with readouts in the control room. These flow channels are powered by the white or yellow vLtal instrument bus. A schiematic of this -AMflow channel ia attached. Channel check and calibration frequencies for the AFW flow channels were included in item 36 of Tanle 15.4.1-I of our proposed Teohnical Specification changes submitted with our let.:.ar to the NPRC dated February 4, 1981. Specific indications for each flow channel available in the control room consistsz of analog meters for each channel with a range of 0-300 g9TM for thc direct to steam generator flow, 0-200 gP4i for the motor-oariven A-w pump flow and 0-400 g•. for the steam-drive-n AFW pump flow.

5. Provide Olectrical cne-linc diagrams for 4160V A.C, 480V AC. 120V AC and 125V DC.

RLE.r"ONSE: E.ectrilac ')ne-iijnu -ijgra.s .' ,i provided In Chaper r !rut ofA, the Fisgu es yind cosC ci :I: have reproduced these figures vnd -. •.close-d them :i h

Hr. Eiarolu R. Denton -4- September 16, 1981

this letter. Please refer also to our letter to M-ir. Denton dated Septe•-ber 11, 1981, which enclosed an instrument bus diagram which reflected modificatione to the instrument bus power supplies.

6. Provide Westinghouse drawings 110E163, Sheets 7, 10, and 12.

RESPONSE3 The drawings are enclosed.

7. Provide alectric-al schematic/elementary diagrams of the AFW aystem annunciation circuits.

RnSPO'ISE: This material was provided at the *ay 11, 1979 meeting with the NRC which uma documented in Mr. Tramell's letter to Licensee dated May 15, 1979. For your convenience, we have vncloseU an additional copy of this material.

8. List all periodic testing performed to demonstrate the operational availability of the Point Beach Units 1 and 2 A.F'W system, including testing .of the automatic initiation logic. Indicate whother this suzveillance ia required by the Point Beach. Units I and 2 Technical 6pecificat icns. f ,

RESPONSE: The periodic testing performed to demonstrate the operationAl availability of the Point Beach AFW system, including testing of the automatic initiation logic, has been provided to the NRC previously. We reference Item 2.1.7 of our letter of Decembez 31, 1979 for logic testing, our proposed Technical Specification changes submitted with. our letter of February 4, 1981 as noted previously in this letter, and the proposed Techiuical Specifications for AFW puw, operability included with our letter dated July 8, 1930.

In response to previous short-term and long-term. kAFW system recommendations, we committed by lettera dated October 29, 1979 and February 4, 1930 to modify the bearing oil cooler water supply for the steam-driven AFli pumps to permit long-term operation of the AFW systeu witibout the need for AC power. Aithougn the NRC Staff review oZ this item has not been com-pleted, we reiterated in our April 9, l961 letter that we were proceeding with this mouification and included our reasons for using the firewater ayotez- and rejecting alternative ddsign... Comipletion of this mcdification has been delayed pending receipt of two pressure reculator valves. Wnen the -ecnlaaor Valvcn are received, w; will complete t'e • inztallation in accordanca wich c0-wr previcuz co-.* Mi •r-.t! t.

!.. liarold R. Denton

Should ycu have any questions rdgarding these responses which cannot be answered by chiecking with the referenced sulzittals or our previous letters, pleas% contact us.

Very truly yours,

C. W. Foa*,D ector Nuclear Power Department

Enclosures

Copy to NRC Resident Inspector (wo/e)

Blind copies to Messrs. C. S. McNeer R. H. Gorske/A. W. Finke Sol Burstein D. K. PortesrG. A. Reed-Gerald Charnoff.

(Copies of enclosure Wi-Thout drawings)

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