GO2-83-553, Recommends Deletion of All Refs to RHR Steam Condensing Sys from Encl Interim Deficiency Rept 216 Re RHR Relief Valve Vents.Steam Condensing Mode of RHR Sys Will Be Deactivated

Recommends Deletion of All Refs to RHR Steam Condensing Sys from Encl Interim Deficiency Rept 216 Re RHR Relief Valve Vents.Steam Condensing Mode of RHR Sys Will Be Deactivated

ML17277A610
Person / Time
Site:	Columbia
Issue date:	06/22/1983
From:	Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML17277A611	List: GO2-83-553, Recommends Deletion of All Refs to RHR Steam Condensing Sys from Encl Interim Deficiency Rept 216 Re RHR Relief Valve Vents.Steam Condensing Mode of RHR Sys Will Be Deactivated
References
GO2-83-553, TAC-60953, NUDOCS 8306270347
Download: ML17277A610 (8)

Text

REGULATORY, FORMATION DISTRIBUTION SY EM (RIDS)

ACCESSION NBR:83062703u7 DOC,DATEs 83/06/2?

NOTARIZED>

NO DOCKET FACIL!50 397 WPPSS Nuclear Projectr Unit 2r Washington Public Powe 05000397

>UT"oNAME AUTHOR AFFILIATION BOUCHEY<G.D, Washington Public Power Supply System RECIPE NAME RECIPIENT AFF II.IATION SCHWKNCERrA ~

licensing Br anch 2

SUBJECT; Recommends deletion of al refs to RHR steam congensing sys from encl Interim Deficiency Rept

?16 re RHR relief -valve vents'team condensing mode of RHR:sys will be deactivated

~

DISTRIBUTION CODE!

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)y Lf TITLE: Licensing Submittal!

PSAR/FSAR.Amdts 8, Related Correspondence NOTES!

RECIPIENT IO CODE/NAME NRR/DL/ADL NRA LB2 I.A INTERNALi ElD/HDS2 IE/DEPER/EPB 36 IE/DEQA/GAB 21 NRR/DE/CEB NRR/OE/EQB 13 NRR/DE/MKB i8 NRA/OE/SAB 24 NRR/OHFS/HFEBOO NRA/DHFS/PSRB NRA/DSI/AEB 26 NRA/DSI/CPB 10 NRA/DSI/ICSB 16 NRR/OSI/PSB 19 NRR/OSI/RSB 23 RGN5 EXTERNAL>> ACRS 01 DMS/DSS (AMDTS)

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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way

" Richland, Washington 99352 (509) 372-5000 June 22, 1983 G02-83-553 Docket No. 50-397 Director of Nuclear Reactor Regulation Attention:

Mr. A. Schwencer, Chief Licensing Branch No.

2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C..

20555

Reference:

NUCL'EAR PROJECT NO.

2 DRAFT TECHNICAL SPECIFICATIONS Letter, G02-83-436, C. S. Carlisle (SS) to J.

B. Martin (NRC Region V), "Nuclear Project No. 2, 10CFR50.55(e)

Potentially Reportable Conditions 8216, RHR Relief Valve Vents; 8213, Standby Liquid Control System (SLCS);

and 8232 LPCS and RHR Support Pin Receptacles, dated May 18, 1983.

(Applicable sections attached.)

The referenced letter provided an interim report on three 10CFR50.55(e) potentially reportable items.

Item one, Condition 8216 concerned a

potential open leakage path (given a failure in the RCIC System) from the primary to the secondary containment through four relief valves in the RHR Steam Condensing System.

The action decided upon by the project is to deactivate the steam condensing mode of the RHR System.

8306270347 830622 PDR ADOCK 05000397 S

PDR qcP I

I

A. Schwencer Page Two June 22, 1983 DRAFT TECHNICAL SPECIFICATIONS The purpose of this letter is to provide Mr. D. Hoffman, NRC/SSPB with the recommendation to delete from the subject document all references to the RHR Steam Condensing System.

Limiting Condition for Operation (LCO) 3.3.2, Tables 3.3.2-1 through -3, and 4.3.2. 1-1, item 5 specifically, should be deleted.

For any additional information, please contact either Mr. M. R. Wuestefeld on (509) 377-2501 extention 2843 or Mr. P.

Powell on extention 2298.

Very truly yours, G.

D. Bouchey

Manager, Nuclear Safety and Regulatory Programs MRW/PLP/tmh Enclosures cc:

R Auluck -

NRC WS Chin

- BPA A

Toth NRC Site D

Hoffman -

NRC

'ernal Oistribution uI.'llen - 905A CS Cailisle - 901A LT Harrold - 901A BA Holmberg - 901A JD Martin - 927M RM Nelson - 905A, PL Powell - 905A GC Sorensen - 340 WW-Waddel - 570 JM Yatabe - 410 CM oower

- 927M Docket File Be/file - 904A PL2/LB BAH/LB "

JDM/LB GDB/LB MRW/LB sf (2) bcc-WG Conn

- B&R RO NS Reynolds

- D&L WNP-2 Files I'

June 22, 1983 G02-83-553 Docket No. 50-397 Director of Nuclear Reactor Regulat'on Attention:

Mr. A. Schwencer, Chief Licensing Branch No.

2 Division of Licensing U.S. Nuclear Regulatory Commission WasNington, D.C.

20555

Subject:

NUCLEAR PROJECT NO, 2

DRAFT TECHNICAL SPECIFICATIONS

Reference:

Letter, G02-83-436, C, S. Carlisle (SS) to J.

B. Martin (NRC Region V), "Nuclear Project No. 2, 10CFR50.55(e)

Potentially Reportab'le Conditions 0216, RHR Relief Valve Vents;

35I213, Standby Liquid Control System (SLCS);

and 4232 LPCS and RHR Support Pin Receptacles, dated May 18, 1983.

(Applicable sections attached.)

The referenced letter provided an interim report on three 10CFR50.55(e) potentially reportable items.

Item one, Condition 4216 concerned a

potential open leakage path (given a failure in the RCIC System} from the primary to the secondary containment through four relief valves in the RHR Steam Condensing System.

The action decided uoon by the project is to deacon'vate

'the""stea condensing mode of the RHR System.

C&t~>

t i

Ih aid K1ii i i.

FOR SIQI<<IATUR8 OF:

QD SECTION FOR APPROVAI. OF APPROVCO T

H rrold BA Hol er Mr

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<<OAT%

l<<IP~7 852I I 88'Q8 88.

4 r g'g tl c 8 IIPIIg

A. Schwencer Page Two June 22, 1983 DRAFT TECHNICAL SPECIFICATIONS The purpose of this letter is to'rGYide Mr, D. Hoffman, NRC/SSPB with

~

the recommendation to dele.e from the subject document all references to the RHR Steam Condensing System.

Limiting Condition for Operation (LCO) 3,3.2, Tables 3.3.2-1 through -3, and 4.3.2.1-1.,

item 5 specifically, should be deleted.

For any additional information, please contact either Rr.

M. R. Muestefeld on (509) 377-2601 extention 2843 or Mr. P. Powell on extention 2298.

'ery truly yours, G. D.'Bouchey Manager, Nuclear Safety and Regulatory Programs MR'H/PLP/tmh Encl'osures cc:

R Auluck - NRC NS Chin

- BPA A

Toth

- NRC Site D

Hof+man -

NRC,"

l". il 88'Qe'98'

HNP-2 AMENDMENT NO ~

33 November 1983 p.

Follw steps n through s of 5.4.6.2.5.1.

5.4.6.2. 5 ~ 3 Steam Condensing

{Hot Standby)

Operation The steam condensing mode of RHR for WNP-2 has been deacti-vated'~

However, the ma)or pieces of equipment are installed with the exception of the steam supply relief valves, RHR-RU-55A and 8 and RHR-RU-95A and 9, and a

e shown on the RCXC and RHR P%XD's {Figures 5.4-9a and b and 5.4-13a and b, respectively).

That equipment which is dedicated to the steam condensing mode will be identified on these figures with reference to the notes identifiying this portion as being deactivated.

NHP>>2 operating procedures have been revised to reflect this deactivation.

Deletion of this mode of operation for RCXC, and RHR will not adversely af feet either systems'apab'lity, to bring the reac or to cold shut-down should, it, be required.

5.4 '.2.5 '

Limiting Single Failure The most limiting single failure in the. combined.function of RCIC and HPCS sys tems is the. fa ilure of HPCS.

If the capa-city of RCXC System is adequate to maintain reactor water level, the operator follows 5.4.6.2.5.1.

Xf however the RCXC capacity is inadequate 5.>.6.2.5.1 applies.

but addi-

'=tionally the operator may also initiat~ the ADS system de'scribed in 6.3.2-t'I 88'Q8'98 5.4-35 gC'fg g

g 58/ gogg

'86 t)Q'-8 P6:24

0 or unusual difficulties without a compensating increase in the level of quality and safety.

Based on the granting of relief from these preservice examination requirements, the staff concludes that the preservice inspection program for MNP-2 is in compliance with 10 CFR 50. 55a(g)(2).

The staff's detailed evalua>>

tion supporting this conclusion is in Appendix K to this report-The initial inservice inspection program has not been submitted.

This program will be evaluated after the applicable ASME Code editior and addenda can be determined based on 10 CFR 50.55a(b),

but before the first refueling outage when inservice inspection begins.

5.4 Com onent and Subs stem Desi n

5.4.2 Residual Heat Removal System 1n a letter dated June 22.

1983, the applicant stated the intention to deacti-vate the steam condensing mode of the residual heat removal (RHR} system at WP-2.

The applicant also requested that specific Technical Specifications that refer to the steam condensing mode of operation be deleted.

The MNP-2 steam condensing mode of the RHR is not safety related and no 'credit is taken for this mode of operation in any safety analyses.

Furthermore, deactivation will no impede the safety function of'tner safety"related modes of the RHR system.

Deactivation of the steam condensing mode is therefore acceptable to the staff.

Th'e Technical Specifications related to the steam condensing mode of operation include l'.mi ing condition for ~pere.i~n

3. 3. ~. Tables

3. 3. 2-1

3. 3. 2-2. 3. 3.2-3.

and 4.3.2. 1-1 (item 5 of each table).

These spec~fications are related to iso-lation actuation instrumentation thai operate valve group 12, which consists of only one valve, E51-F064.

Deactivation of the steam condensing made involves locking closed and removing power from valve E51-F064.

This obviates the need for automatic iso~ation and. therefore, de~eting these soecifications is acceptable.

MNP-2 SSER 4 5'2 Se QG'~ec 6st" z'2 6BQ NA8d