GNRO-2004/00014, Technical Specification Bases Update to NRC for Period Dated February 12, 2004

Technical Specification Bases Update to NRC for Period Dated February 12, 2004

ML040480326
Person / Time
Site:	Grand Gulf
Issue date:	02/12/2004
From:	Bottemiller C Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2004/00014
Download: ML040480326 (8)

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Waterloo Road P.O. Box 756 Pori Gibson. MS 39150 Tel 601 437 6299 Manager Plant Licensing GNRO-2004/00014 February 12,2004 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Technical Specification Bases Update to the NRC for Period Dated February 12, 2004 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 Ladies and Gentlemen:

Pursuant to Grand Gulf Nuclear Station (GGNS) Technical Specification 5.5.11, Entergy Operations, Inc. hereby submits an update of all changes made to GGNS Technical Specification Bases since the last submittal (GNRO-2004/00002 letter dated January 22, 2004 to the NRC from GGNS). This update is consistent with update frequency listed in 10CFR50.71(e).

This letter does not contain any commitments.

Should you have any questions, please contact Michael Larson at (601) 437-6685.

Yours truly, CAB/MJL attachment: GGNS Technical Specification Bases Revised Pages cc: (See Next Page)

GNRO-2004/00014 PAGE 2 of 2 cc:

Hoeg T. L. (GGNS Senior Resident) (w/a)

Levanway D. E. (Wise Carter) (w/a)

Reynolds N. S. (w/a)

Smith L. J. (Wise Carter) (w/a)

Thomas H. L. (w/o)

US. Nuclear Regulatory Commission ALL LETTERS ATTN: Mr. Bruce Mallett (w/2) 61 1 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U S . Nuclear Regulatory Commission ALL LETTERS - COURIER ATTN: Mr. Bhalchandra Vaidya, NRR/DLPM (WE) DELIVERY (FEDEX, ETC.)

ATTN: ADDRESSEE ONLY ADDRESS ONLY - ****DO ATTN: Courier Delivery Only NOT USE FOR U.S. POSTAL Mail Stop OWFN/7D-1 SERVICE ADDRESS*****

11555 Rockville Pike Rockville, MD 20852-2378

ATTACHMENT to GNRO-2004/00014 Grand Gulf Technical Specification Bases Revised Pages dated February 12,2004 I LDC# BASES PAGES AFFECTED TOPIC of CHANGE 03039 B 3.3-160, B 3.3-160a, B Technical Specification Amendment 163 implementation 3.3-170a, B 3.3-171 03045 B 3.6-105 Technical Specification Amendment 164 implementation

P r i m a r y Containment and D r y w e l l I s o l a t i o n I n s t r u m e n t a t i o n B 3.3.6.1 BASES APPLICABLE 5.b. R e a c t o r Vessel Water Level-Low. Level 3 (continued)

SAFETY ANALYSES, LCO, and Water L e v e l -Low, Level 3 F u n c t i o n a r e r e q u i r e d t o be APPLI C A B 1 L I TY OPERABLE i n MODES 4 and 5 ( b o t h c h a n n e l s must i n p u t i n t o t h e same t r i p system) p r o v i d e d t h e RHR Shutdown C o o l i n g System in t e g r i t y is m a i n t a i n e d . System i n t e g r i t y is m a i n t a i ned p r o v i d e d t h e p i p i n g i s i n t a c t and no m a i n t e n a n c e i s b e i n g p e r f o r m e d t h a t has t h e p o t e n t i a l f o r d r a i n i n g t h e r e a c t o r v e s s e l t h r o u g h t h e system. When o n l y one t r i p s y s t e m i s OPERABLE i n MODE 4 o r 5, t h e t r i p system s h o u l d be c o n s i d e r e d i n o p e r a b l e i f t h e a s s o c i a t e d RHR Shutdown C o o l i n g System s u c t i o n f r o m t h e r e a c t o r v e s s e l i s o l a t i o n v a l v e

( i . e . , t h e lE12-FO08 o r lE12-FO09) i s n o t a s s o c i a t e d w i t h an OPERABLE d i e s e l g e n e r a t o r . When n e i t h e r t r i p system i s r e q u i r e d t o be OPERABLE i n MODE 5 , t h e a p p l i c a b l e s a f e t y a n a l y s i s assumes t h a t t h e RHR shutdown c o o l ing isol a t i on v a l v e s a r e e a s i l y r e c o v e r a b l e ( s u c h as b y m a i n t a i n i n g a t l e a s t one v a l v e c a p a b l e o f b e i n g r e m o t e l y c l o s e d a f t e r r e e n e r g i z i n g t h e v a l v e ) such t h a t a d r a i n down e v e n t t h r o u g h t h e shutdown c o o l i n g f l o w p a t h can be t e r m i n a t e d p r i o r t o r e a c h i n g L e v e l 3 by c l o s i n g one o r more o f t h e Shutdown C o o l i n g System i s o l a t i o n v a l v e s . Based on t h e a n a ' i y s i s o f t h e t i m e a v a i l a b l e t o m i t i g a t e a l l p o s t u l a t e d d r a i n down e v e n t s , t h i s c o n d i t i o n , i n i t s e l f , i s n o t c o n s i d e r e d an OPDRV.

The R e a c t o r Vessel Water L e v e l -Low, Level 3 A l l o w a b l e Value was chosen t o be t h e same as t h e RPS R e a c t o r Vessel Water Level-Low, L e v e l 3 A l l o w a b l e V a l u e (LCO 3.3.1.11 s i n c e t h e c a p a b i l i t y t o cool t h e f u e l may be t h r e a t e n e d .

The R e a c t o r Vessel Water Level-Low, Level 3 F u n c t i o n i s r e q u i r e d t o be OPERABLE i n MODE 3 w i t h r e a c t o r p r e s s u r e l e s s t h a n t h e RHR p e r m i s s i v e p r e s s u r e , MODE 4, and MODE 5 t o prevent t h i s p o t e n t i a l f l o w p a t h from l o w e r i n g r e a c t o r vessel l e v e l t o t h e t o p o f t h e f u e l . This instrumentation i s r e q u i r e d t o be OPERABLE i n MODES 1 and 2 and i n MODE 3 w i t h r e a c t o r steam dome p r e s s u r e g r e a t e r t h a n o r e q u a l t o t h e RHR c u t - i n p e r m i s s i v e p r e s s u r e t o s u p p o r t a c t i o n s t o e n s u r e t h a t o f f s i t e dose l i m i t s o f l O C F R l O O a r e n o t exceeded.

T h i s F u n c t i o n i s o l a t e s t h e Group 3 v a l v e s .

GRAND GULF B 3.3-160 LDC 03039

Primary Containment and D r y w e l l I s o l a t i o n I n s t r u m e n t a t i o n B 3.3.6.1 BASES APPLICABLE 5.c. R e a c t o r Steam Dome P r e s s u r e - H i q h SAFETY ANALYSES, LCO, and The Shutdown C o o l i n g System R e a c t o r Steam Dome P r e s s u r e -

APPLICABILITY H i g h F u n c t i o n i s p r o v i d e d t o i s o l a t e t h e shutdown c o o l i n g

( c o n t i nued 1 p o r t i o n o f t h e RHR System. T h i s i n t e r l o c k i s p r o v i d e d o n l y f o r equipment p r o t e c t i o n t o p r e v e n t an i n t e r s y s t e m LOCA s c e n a r i o and c r e d i t f o r t h e i n t e r l o c k i s n o t assumed i n t h e a c c i d e n t o r t r a n s i e n t a n a l y s i s i n t h e UFSAR.

The R e a c t o r Steam Dome-High p r e s s u r e s i g n a l s a r e i n i t i a t e d from f o u r transmitters. Fo u r c h a n n e l s o f R e a c t o r Steam Dome P r e s s u r e - H i g h F u n c t i o n a r e a v a i l a b l e and a r e r e q u i r e d t o be OPERABLE t o e n s u r e t h a t no s i n g l e i n s t r u m e n t f a i l u r e can p r e c l u d e t h e is o l a t i on f u n c t i on. The A1 1owabl e V a l u e was chosen t o be l o w enough t o p r o t e c t t h e s y s t e m e q u i p m e n t f r o m overpressurization.

T h i s F u n c t i o n i s o l a t e s t h e Group 3 v a l v e s .

(continuedl GRAND GULF B 3.3-160a LDC 03039

Primary Containment a n d Drywell I s o l a t i o n Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.8 (continued)

REQUIREMENTS instrument response times a n d assure operation of t h e analyzed instrument loops within acceptable l i m i t s .

Reference 7 a l s o i d e n t i f i e s t h a t t h e r e a r e no known channel sensor f a i 1 ure modes i d e n t i f i e d t h a t can be detected by response time t e s t i n g t h a t cannot a l s o be detected by other Techni cal Speci f i c a t i o n requi red survei 11 ances. Theref o r e ,

when t h e requi rements, i ncl u d i ng sensor t y p e s , of Reference 7 a r e complied w i t h , adequate assurance o f t h e response time of t h e sensors i s provided. This assurance of t h e response time of t h e sensors when combined w i t h t h e response time t e s t i n g of t h e remainder of the channel ensures t h a t t h e individual channel response times a r e l e s s t h a n o r equal t o the maximum values assumed i n t h e accident a n a l y s i s . The c a l i b r a t i o n s h a l l be performed such t h a t f a s t ramp o r s t e p change t o system components d u r i n g c a l i b r a t i o n s i s performed t o v e r i f y t h a t t h e response of t h e t r a n s m i t t e r t o t h e i n p u t change i s prompt. Technicians s h a l l moni t o r f o r response time degradati on during the performance of cal i b r a t i ons.

Technicians s h a l l b e appropriately t r a i n e d t o ensure t h e y a r e aware o f the consequences of instrument response time degradation. These items a r e commitments made per Reference

8. I f t h e a l t e r n a t e t e s t i n g requirements of Reference 7 a r e not complied w i t h then t h e e n t i r e channel w i l l be response time t e s t e d i ncl u d i ng t h e sensors.

ISOLATION SYSTEM RESPONSE TIME t e s t s f o r t h i s instrumentation a r e conducted on a n 18 month STAGGERED TEST BASIS. T h i s t e s t Frequency i s c o n s i s t e n t w i t h t h e t y p i c a l i n d u s t r y refuel i ng cycl e a n d i s based upon pl a n t operati n g experience t h a t shows t h a t random f a i l u r e s o f instrumentation components causing s e r i o u s response time degradation, b u t not channel f a i l u r e , a r e i n f r e q u e n t .

A n a l y s i s has shown t h a t with t h e upper containment pool c a v i t y flooded a n d the g a t e s removed, adequate time e x i s t s t o allow operator a c t i o n necessary t o t e r m i n a t e t h e inventory l o s s p r i o r t o reaching r e a c t o r level 3. This a n a l y s i s takes c r e d i t f o r t h e pool level b e i n g g r e a t e r t h a n or equal t o 22 f e e t 8 inches above t h e r e a c t o r vessel f l a n g e . Verifying t h e upper containment pool l e v e l i s g r e a t e r t h a n o r equal t o 22 f e e t 8 inches on a f o u r hour frequency provides assurance t h a t t h e o p e r a t o r s have enough time t o d e t e c t a n d terminate a d r a i n down event.

(continued) I GRAND G U L F 6 3.3-170a LDC 03039

Primary Containment a n d Drywell I s o l a t i o n Instrumentation 8 3.3.6.1 BASES (continued) I REFERENCES 1. UFSAR, Chapter 6. I

2. UFSAR, Chapter 15.

3. NEDO-31466, "Technical S p e c i f i c a t i o n Screening Cri t e r i a Appl i c a t i o n a n d Ri sk Assessment ,"

November 1987.

4. UFSAR, Section 9.3.5.

5. NEDC-31677-P-A, "Technical S p e c i f i c a t i o n Improvement Analysis f o r BWR I s o l a t i o n Actuation I n s t r u m e n t a t i o n , "

June 1989.

6. NEDC-30851-P-A, Supplement 2 , "Technical S p e c i f i c a t i o n s Improvement Analysis f o r BUR I s o l a t i o n Instrumentation Common t o RPS a n d ECCS Instrumentation, " March 1989.

7. NEDO-32291-A, "System Analyses f o r Elimination o f Selected Response Time Testing Requi rements," October 1995.

a. GNRI-97/00181, Amendment 133 t o t h e Operating License.

GRAND G U L F B 3.3-171 LDC 03039

Drywell B 3.6.5.1 BASES SURVEILLANCE SR 3.6.5.1.1 (continued)

REQUIREMENTS the safety analysis. This Survei77ance i s performed a t l e a s t once every 10 years on a performance based frequency.

This frequency i s modified on a one-time basis u n t i l November 23, 2008. The Frequency i s consistent w i t h the d i f f i c u l t y o f performing the t e s t , risk o f h i g h radiation I

exposure, and the remote possibility t h a t s u f f i c i e n t component f a i 1 ures w i 11 occur such t h a t the drywe7 1 bypass leakage l i m i t will be exceeded. I f during the performance of t h i s required Surveil 1 ance the drywell bypass 1 eakage rate i s greater t h a n the drywell bypass leakage l i m i t the Surveillance Frequency i s increased t o every 48 months. I f during the performance of the subsequent consecutive Surveillance the drywell bypass leakage rate i s l e s s t h a n or equal t o the drywell b y p a s s leakage limit the 10 year Frequency may be resumed. I f during the performance of two consecutive Survei 11 ances the drywell bypass 1ea kage i s greater t h a n the drywell bypass leakage limit the Surveillance Frequency i s increased t o a t l e a s t once every 24 months. The 24 months Frequency i s m a i n t a i n e d u n t i l duri ng the performance of two consecutive survei 11 ances the drywell bypass leakage rate i s less t h a n or equal t o the drywell bypass leakage l i m i t , a t which time the 1 0 year Frequency may be resumed. For two Surveillances t o be considered consecutive the Surveil1 ances must be performed a t l e a s t 12 months apart.

Since the Frequency i s performance based, the Frequency was concl uded t o be acceptable from a re1 i a b i 1 i t y standpoint (Ref. 3 ) .

SR 3.6.5.1.2 The exposed accessi bl e drywell i n t e r i o r and exterior surfaces are inspected t o ensure there are no apparent physical defects t h a t would prevent the drywell from performing i t s intended function. T h i s SR ensures t h a t drywell structural i n t e g r i t y i s maintained. The Frequency was chosen so t h a t the i n t e r i o r a n d exterior surfaces of the drywell can be inspected in conjunction w i t h the inspections of the primary containment required by 10 CFR 50, Appendix J (Ref. 2 ) . Due t o the passive nature of the drywell structure, the specified Frequency i s sufficient t o identify (con t i nuedl GRAND GULF B 3.6-105 LDC 03045