ML20065D374

Forwards Rev to Relief Request 10-VRR-2 Re RHR stay-fill Supply Check Valves,Per

ML20065D374
Person / Time
Site:	Peach Bottom
Issue date:	09/11/1990
From:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9009250152
Download: ML20065D374 (7)

Text

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10 CPR 50.550 I

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PHILADELPHIA ELECTRIC COMPANY  !

l NUCLEAR GROUP HEADQUARTERS 955 65 CHESTERBROOK BLVD. [

WAYNE. PA 19087 5691 f (ris) soo sooo  :

September 11, 1990 Docket Nos. 50-277 50-278 i License Nos. DPR-44 DPR-56 U.S. Nuclear Regulatory Commission  !

Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Peach Bottom Atomic Power Station, Units 2 and 3  !

Inservice Testing Program

REFERENCE:

Letter from J. W. Gallagher (PECo) to W. R. Butler (NRC) dated June 29, 1988 Dear Sir f

In the above referenced letter, Philadelphia Electric Company (PECo) submitted a revised second 10-year interval Inservice Testing (IST)-Program for Peach Bottom Atomic Power Station, Units 2 and 3. This revised IST Program is currently under NRC review. The purpose of this letter is to supplement the referenced submittal.

Enclosed with this letter is Relief Request No. 10-VRR-2, Revised 9/90 and its associated valve table changes. This is a revision to Relief Request 10-VRR-2 which was included in the referenced submittal. This Relief Request concerns the Residual Heat Removal stay-fill supply check valves. The proposed alternate ,

testing is to test the valves in pairs. The previously proposed alternate testing was to perform valve disassembly.

In the referenced submittal, we-also provided Relief '

-Requests 33-PRR-1 and 48-PRR-1. These requested relief from the flow measurement requirements for the Emergency Service Water (ESW) pumps, ESW booster pumps and Emergency Cooling Water pump until-modifications can be. completed to allow flowrates to be measured.

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9009250152 900911 -

M //d fR ADOCK 05000277

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docurant Control Desk S ptC bar 11, 1990 Inc.orvica TOsting Program Page 2 An appropriate modification, common to both units, will be completed prior to startup from the next Unit 2 refueling outages therefore, only schedular relief from performing flow measurement is requested.

The current design for the proposed modification incorporates the use of ultrasonic testing. It is our understanding thrt this flow measuring technique, provided it meets applicable ASME code requirements, does not need a Relief Request.

If you have any questions concerning this request, please do not hesitate to call.

Very truly yours, 6m c 4 G. A. Hunger, Jr.

Manager-Licensing Nuclear Engineering & Services Enclosure cct T. T. Martin, Administrator, f.egion I, USNRC J. J. Lyash, USNRC Senior Resident Inspector

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. PBAPS 283 IST Procrco App ndix C

. Page 9 of 23 RELIEF REQUEST N0. 10-VRR-2, Revised 9/90 S'stemt

, Residual Heat Removal (RHR)

Valve t s ): CHK-2-10-063 CHK-3 10-063  !

l CHK-2-10-064 CHK-3 .0-064 CHK-2-10-183A,B CHK-3-11-183A,8 l ,

CHK-2-10-184A,B CHK-3-10-184A,8

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i categopy C j Functions Residual Heat Removal /LPCI Stay-fill supply check valves. l Testing 3equirement(s): Exercise in the reverse direction, i

Basis for Relieft The above stay-fill check valves are installed in pairs (series l arrangements) with no provisions for individual valve testing I (ie CHK-10-063 & 064 are in series: CHK-10-183 & CHK-10-184 are in series). The valves function, in series as a pair, to prevent losu of RHR inventort a the stay-fill system in the event of a stay-fill system silure. Because testing these valves as a pair is preferable to valve disassembly and inspection, relief from testing individual valves is requested, i In addition. Technieml Specification 3.5.0 requires that the l discharge piping of the LPCI system be filled to prevent water 1 hammer upon system initiation. Testing these valves during power operation would make the stay-fill system inoperable, requiring entry into the associated limiting condition for operation, for this reason, testing of the above pairs of  ;

valves will be performed at cold shutdowns.

Alternate Testingt Valves will be tested as a pair in the reverse direction at cold shutdown. Both valves in the pair will - be considered inoperable if testing indicates the valves do not-close on i reverse flow.

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IST TABLE - VALVES PAGE NO. 77 PEACM 80TTCpt ATONIC POWE= STATION - tmIT 8 2 & CopequN DATE 07/24/90 SYSTED: 10 RESIDUAL MEAT REMOWAL (R*Mt)

VALVE VALVE ACT/ VALVE ACT. POSITIONS APP. J TEST - FREO. VIIR/VCS NUMBER PEID COORD CAT. PAS } Jig TYPE TYPE Net SA.F F.A. l TYPE C (DIRECTION) tRfGER _ REMARKS F-4 A, C A 24 TC SA C OC -

Y ET-C(FM), LJ-T, 10-VCS-1, PENT. N-135 A0-3-90-046A M-361 (SMT 1)

LP-T, PI-T GWRR-1 M-361 (SMT 2) F-6 A, C A 24 TC SA C OC - Y ET-C(FM), LJ-T, 10-VCS-1 PENT. N-134 A0-3-10-046s LP-T, PI-T GWRR-1 E-4 A P 1 GL Ao C C C Y LJ-T, LP-T, PI-T Gvest-1 PEAT. 5-13s AO-3-10-1634 M-361 (SMT 1)

F-6 A P 1 GL A0 C C C Y LJ-T, LP-T, PI-T GWIMt-1 PENT. N-134 A0-3-10-163s M-361 (SMT 2)

A-5 A 3 CK SA OC OC - N ET-0(F), ET-R(R) 10-vRR-1 Cw-3-10-019A M-361 (SMT 1) C M-361 (SMT 2) C-5 C A 3 CK SA OC OC - N ET-0(F), ET-R(R) 10-Vitt-1 CM-3-10-019s M-361 (SMT 1) C-5 C A 3 CK SA OC OC -

N ET-O(F), ET-R(R? 10-wRR-1 CM-3-10-019C CW-3-10-019D M-361 (SMT 2) A-5 C A ) CK SA OC OC -

N ET-0(F), ET-R(R) 10-VINt-1 CW-3-10-048A M-361 (SMT 1) A-6 C A 20 TC SA OC OC -

N ET-0(F8R)

CW-3-?o-04as M-361 (SMT 2) C-4 C A 20 TC SA OC OC - N ET-0(F88t)

CNet-3-10-048C M-361 (SMT 1) s-6 C A 20 TC SA OC OC -

N ET-0(Falt) -

CMIC-3-10-048D M-361 (SMT 2) A-4 C A 20 TC S4 OC OC - N ET-0(F81t)

G-5 C A 2 CK - SA OC C - N ET-C(R) 10-vsNt-2 CW-3-10-064 M-361 (SMT 1)

G-5 C A 2 CK SA OC C -

N ET-C(R) 10-WINt-2 CMK-3-90-184A M-361 (SMT 1)

G-4 C A 2 CK SA OC C - N ET-C(R) 10-vmR-2 CMK-3-10-1848 M-361 (SMT 2)

M-361 (SMT 1) s-4 8 A 24 GT MO O OC Al N ET-0, ST-0(OSC),

MO-3-10-013A PI-T M-361 (SMT 2) C-6 s A 24 GT MO O OC Al N ET-0, ST-0(OSC),

MO-3-10-013e w_ . . _ . . - .. _ _ _ _-

f IST TABLE - VALVES PAGE me. TTA PEACM 90TTOM ATOMIC POWER STATION - UNIT # 2 & CepeDE DATE 07/24/90 SYSTEM: 10 RESIDUAL MEAT REMOVAL (RnR)

VALVE VALVE ACT/ VALVE ACT. POS!?t0NS APP. J TEST - FRES. VRR/VCS NLpl8ER P&!D M CAT. M M T'PE TYPE _ NRM E E E (D!RECTION) IRSWER REMMKS CMK-2-10-063 M-361 (Snr 1) G-5 C A 2 CK SA OC C - F ET-C(R) 10-VRR-2 Clat-2-10-183A M-361 (Sur 1) G-5 C A 2 CA SA OC C - N ET-C(R) 10-VRR-2 Cnt-a-10-1838 M-361 (SNT 2) G-4 C A 2 CK SA OC C -

N ET-C(R) 10-VRet-2 i

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l IST TASLE - VALVES PAGE WD. 77 PEACM SOTTOM ATOMIC POWER STATION - tJNIT # 3 DATE 07/24/90 -

SYSTED: 10 RESIDUAL MEAT REMOVAL (RnR)

VALVE VALVE ACT/ VALVE ACT. POSITIONS APP. J TEST - FRES. WWR/VCS MUPGEE P&ID g CAT. $ g TYPE TYPE M E E TYPE C (DIRECTION) IR5GER REMARKS i

A0-3-10-0664 'M-361 (SMT 3) F-4 A, C A 24 TC SA C OC - Y ET-C(F8R), LJ-T, ~ 10-VCS-1, PENT. N-135 LP-T, PI-T GWER-1

. AO-3-10-046s M-361 (SMT 4) F-6 A, C A 24 TC SA C OC -

Y ET-C(FM), LJ-T, 10-VCS-1 PEWT. 5-13A LP-T, PI-T GVER-1 4

A0-3-10-163A M-361 (SMT 3) E-4 A P 1 GL AO C C C Y LJ-7, LP-T, PI-T GwnR-1 PENT. N-138 -

A0-3-10-1638 M-361 (SMT 4) F-6 A P 1 GL AD C C C Y LJ-T, LP-T, PI-T GwmR-1 " PERT. m-13A CM-3-10-0194' M-361 (SMT 3) A-5 C A 3 CK SA OC OC - u ET-O(F), ET-R(R) 10-VeR-1 CM-3-10-019e M-361 (SMT 4) C-5 C A 3 CK SA OC OC - 4 ET-G(F), ET-R(R) 10-vnt-1 CE-3-10-019C M-361 (SMT 3) C-5 C A 3 CK SA OC OC - N ET-0(F), ET-R(R) 10-wtR-1 CM-3-10-0190 M-361 (SMT 4) A-5 C A 3 CK SA OC OC - W ET-0(F), ET-R(R) 10-44R-1 CM-3-10-048A M-361 (SMT 3) A-6 C A 20 TC SA OC OC -

N ET-0(FSR)

CE-3-10-068s M-361 (Sui 4) C-4 C A 20 TC SA OC OC - # ET-0(FSR)

CM-3-10-048C M-361 (SMT 3) 8-6 C A 20 TC SA OC OC - M ET-0(F84)

.i CM-3-10-068D M-361 (Sni 4) A-4 C A 20 TC SA OC OC - N ET-0(FER)

CM-3-10-064 M-361 (Snf 3) G-5 C A 2 CK SA OC^ C - N ET-C(R) 10-wat-2 Cw-3-10-184A M-361 (SNT 3) G-5 C A 2 CK SA OC C -

N ET-C(R) 10-vet-2 CM-3-10-186s M-361 (SMT 4)- G C A 2 CK SA - OC C -

N ET-C(R) 16 vut-2 MO-3-19-013A M-361 (SMT 3) 5-4 5 A 24 GT' MO O' OC At t ET-8, ST-6(OSC),

PI-T MO-3-10-0138 M-361 (SMT 4) C-6 8 A 24 GT M0 O OC .Al N ET-0, SI-e(OSC),

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