GNRO-2007/00019, Technical Specification Bases Update to the NRC for Period Dated March 30, 2007

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Technical Specification Bases Update to the NRC for Period Dated March 30, 2007
ML070950060
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Site: Grand Gulf Entergy icon.png
Issue date: 03/30/2007
From: Bottemiller C
Entergy Operations
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Document Control Desk, NRC/NRR/ADRO
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GNRO-2007/00019
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Entergy Operations, Inc.

Waterloo Road P.O. Box 756 Port Gibson, MS 39150 Tel 601 437 6299 Charles A. Bottemiller Manager Plant Licensing GNRO-2007/00019 March 30, 2007 U.S.Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Technical Specification Bases Update to the NRC for Period Dated March 30, 2007 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29

Dear Sir and Madam:

Pursuant to Grand Gulf Nuclear Station (GGNS) Technical Specification 5.5.1 1, Entergy Operations, Inc. hereby submits an update of all changes made to GGNS Technical Specification Bases since the last submittal (GNRO-2006100054 letter dated September 28, 2006 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 James Owens at (601) 437-6219.

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

GNRO-2007/00019 Page 2 cc:

NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ALL LETTERS ATTN: Dr. Bruce S. 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/DORL (w/2) DELIVERY (FEDEX, ETC.)

ADDRESS ONLY *"DO ATTN: ADDRESSEE ONLY NOT USE FOR US.

ATTN: Courier Delivery Only POSTAL SERVICE Mail Stop OWFN/ 0-7D1A ADDRESS**"

11555 Rockville Pike NOT USED IF EIE USED Rockville, MD 20852-2378

ATTACHMENT to GNRO-2007/00019 Grand Gulf Technical Specification Bases Revised Pages dated March 30, 2007 LDC# BASES PAGES AFFECTED TOPIC of CHANGE 07019 B 3.9-25, 26, 27, 28, 28a, 29, 30, Revise the wording to provide clarification of shut down and 33 cooling temperature limits and include a reference to the ER performing the evaluation.

07008 B 3.10-1, l a , 3, and 3a Provide clarification on Inservice Leak and Hydrostatic Testing Operations

RHR- High Water Level B 3.9.8 B 3.9 REFUELING OPERATIONS B 3.9.8 Residual H e a t Removal (RHR)-High W a t e r Level BASES BACKGROUND The purpose o f t h e RHR System i n MODE 5 i s t o remove decay heat and s e n s i b l e h e a t from t h e r e a c t o r c o o l a n t , as r e q u i r e d by GDC 34. Each o f t h e two shutdown c o o l i n g l o o p s o f t h e RHR System i s designed t o m a i n t a i n t h e r e a c t o r c o o l a n t b u l k average temperature as r e q u i r e d . Each l o o p c o n s i s t s o f one I motor d r i v e n pump, two heat exchangers, and a s s o c i a t e d p i p i n g and v a l v e s . Both loops have a common s u c t i o n f r o m t h e same r e c i r c u l a t i o n l o o p or s u c t i o n can be a l i g n e d from t h e f u e l p o o l . Each pump discharges t h e r e a c t o r c o o l a n t ,

a f t e r i t has been cooled by c i r c u l a t i o n t h r o u g h t h e r e s p e c t i v e heat exchangers, t o t h e r e a c t o r v i a separate feedwater l i n e s o r t o t h e upper containment p o o l v i a a common s i n g l e f l o w d i s t r i b u t i o n sparger, o r t o t h e r e a c t o r v i a t h e l o w p r e s s u r e c o o l a n t i n j e c t i o n path. The RHR heat exchangers t r a n s f e r heat t o t h e Standby S e r v i c e Water System. The RHR shutdown c o o l i n g mode i s manually c o n t r o l 1ed.

An A l t e r n a t e Decay H e a t Removal System (ADHRS) i s a l s o a v a i l a b l e t o p r o v i d e t h e r e q u i r e d decay h e a t removal. The ADHRS p r o v i d e s a s i n g l e subsystem c o n s i s t i n g o f two motor d r i v e n pumps, two heat exchangers, and a s s o c i a t e d p i p i n g and valves. The system u t i l i z e s t h e common RHR shutdown c o o l i n g s u c t i o n l i n e and some f u e l pool c o o l i n g and cleanup p i p i n g .

The system i s n o t s a f e t y - r e l a t e d and cannot be powered from an o n s i t e d i e s e l generator. The ADHRS heat exchangers t r a n s f e r heat t o t h e P l a n t Service Water System (PSW). The ADHRS i s manually c o n t r o l l e d and i s o l a t e d f r o m t h e common p o r t i o n s o f t h e o t h e r systems.

I n a d d i t i o n t o t h e above subsystems, t h e volume o f water above t h e r e a c t o r pressure vessel ( R P V ) flange p r o v i d e s a heat s i n k f o r decay heat removal.

APPLICABLE With t h e u n i t i n MODE 5, n e i t h e r t h e RHR System n o r t h e SAFETY ANALYSES ADHRS i s r e q u i r e d t o m i t i g a t e any events o r a c c i d e n t s evaluated i n t h e s a f e t y analyses. The RHR System, or t h e ADHRS, i s r e q u i r e d f o r removing decay heat t o m a i n t a i n t h e temperature o f t h e r e a c t o r coolant.

( c o n t in w GRAND GULF B 3.9-25 LDC 07019

RHR - H i g h Water Level 6 3.9.8 BASES APPLICABLE A l t h o u g h t h e RHR System does n o t meet a s p e c i f i c c r i t e r i o n SAFETY ANALYSES o f t h e MRC P o l i c y Statement, i t was i d e n t i f i e d i n t h e NRC (continued) P o l i c y Statement as an i m p o r t a n t c o n t r i b u t o r t o r i s k r e d u c t i o n . T h e r e f o r e , t h e RHR System i s r e t a i n e d a s a S p e c i f i c a t i o n . The ADHRS i s i n c l u d e d i n t h e S p e c i f i c a t i o n t o p r o v i d e r e q u i r e m e n t s f o r decay h e a t removal c a p a b i l i t y d u r i n g an outage w h i l e t h e RHR System i s o u t o f s e r v i c e .

Leo Only one RHR shutdown c o o l i n g subsystem i s r e q u i r e d t o be OPERABLE i n MODE 5 w i t h i r r a d i a t e d f u e l i n t h e RPV and t h e w a t e r l e v e l 2 22 f t 8 i n c h e s above t h e RPV f l a n g e . Only one subsystem i s r e q u i r e d because t h e volume o f w a t e r above t h e RPV f l a n g e p r o v i d e s backup decay h e a t removal c a p a b i l i t y .

The c u r r e n t r e q u i r e m e n t s f o r decay h e a t removal are: I n MODE 5 w i t h no i n t e r f a c e between vessel b u l k c o o l a n t and spent f u e l p o o l , t h e requirement i s s 155°F.

I n MODE 5 w i t h vessel b u l k c o o l a n t i n t e r f a c i n g w i t h t h e spent f u e l p o o l , t h e requirement i s s 140°F.

An OPERABLE RHR shutdown c o o l i n g subsystem c o n s i s t s of an RHR pump, two h e a t exchangers, v a l v e s , p i p i n g , i n s t r u m e n t s ,

and c o n t r o l s t o ensure an OPERABLE f l o w path. The r e q u i r e d RHR shutdown c o o l i n g subsystem must have a OPERABLE d i e s e l g e n e r a t o r capable o f s u p p l y i n g e l e c t r i c a l power.

A d d i t i o n a l l y , each RHR shutdown c o o l i n g subsystem i s c o n s i d e r e d OPERABLE i f i t can be manually a l i g n e d (remote o r l o c a l ) i n t h e shutdown c o o l i n g mode f o r removal o f decay heat. O p e r a t i o n ( e i t h e r continuous o r i n t e r m i t t e n t ) o f one decay h e a t removal subsystem ( e i t h e r RHR o r ADHRS) can m a i n t a i n and reduce t h e r e a c t o r c o o l a n t temperature as r e q u i r e d . However, t o ensure adequate c o r e f l o w t o a l l o w f o r a c c u r a t e average r e a c t o r c o o l a n t temperature m o n i t o r i n g ,

n e a r l y continuous o p e r a t i o n i s r e q u i r e d . A Note i s p r o v i d e d t o a l l o w a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> e x c e p t i o n f o r t h e o p e r a t i n g subsystem t o n o t be i n o p e r a t i o n every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

APPLICABILITY One RHR shutdown c o o l i n g subsystem must be OPERABLE i n MODE 5, w i t h i r r a d i a t e d f u e l i n t h e RPV and t h e w a t e r l e v e l 2 22 f t 8 i n c h e s above t h e t o p o f t h e RPV f l a n g e , t o p r o v i d e decay heat removal. RHR System requirements i n o t h e r MODES

-~

GRAND GULF B 3.9-26 LDC 07019

RHR- High Water L e v e l B 3.9.8 R4SES I

~

APPLICABILITY (continued) a r e covered b y LCOs i n S e c t i o n 3.4, Reactor Coolant System

( R C S ) ; Section 3.5, Emergency Core C o o l i n g Systems ( E C C S )

I and Reactor Core I s o l a t i o n C o o l i n g ( R C I C ) System; and S e c t i o n 3 . 6 , Containment Systems. RHR Shutdown Cooling System requirements i n MODE 5, w i t h t h e water l e v e l < 22 f t 8 inches above t h e RPV f l a n g e , a r e g i v e n i n LCO 3.9.9, "Residual Heat Removal ( R H R I - Low Water Level ."

ACTIONS N I t h no RHR shutdown c o o l i n g subsystem OPERABLE, an a l t e r n a t e method of decay heat removal must be e s t a b l i s h e d w i t h i n 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. I n t h i s c o n d i t i o n , t h e volume o f water above t h e RPV flange p r o v i d e s adequate c a p a b i l i t y t o remove decay h e a t from t h e r e a c t o r core. However, t h e o v e r a l l r e l i a b i l i t y i s reduced because loss of water l e v e l c o u l d r e s u l t i n reduced decay heat removal c a p a b i l i t y . The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time i s based on t h e decay heat removal f u n c t i o n and t h e p r o b a b i l i t y of a l o s s o f t h e a v a i l a b l e decay heat removal c a p a b i l i t i e s . Furthermore, v e r i f i c a t i o n o f t h e f u n c t i o n a l a v a i l a b i l i t y o f these a l t e r n a t e method(s) must reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> t h e r e a f t e r . T h i s w i l l ensure c o n t i n u e d heat removal c a p a b i l i t y .

A l t e r n a t e decay heat removal methods a r e a v a i l a b l e t o t h e o p e r a t o r s f o r r e v i e w and p r e p l a n n i n g i n t h e u n i t ' s Operat Procedures. For example, t h i s may i n c l u d e t h e use o f t h e Reactor W a t e r Cleanup System, o p e r a t i n g w i t h t h e r e g e n e r a t i v e heat exchanger bypassed. The method used t o remove t h e decay heat should be t h e most prudent choice based on u n i t c o n d i t i o n s .

I f no RHR shutdown c o o l i n g subsystem i s OPERABLE and an a l t e r n a t e method o f decay heat removal i s n o t a v a i l a b l e i n accordance w i t h Required A c t i o n A . 1 , a c t i o n s s h a l l be taken immediately t o suspend o p e r a t i o n s i n v o l v i n g an increase i n r e a c t o r decay heat l o a d by suspending t h e l o a d i n g o f i r r a d i a t e d f u e l assemblies i n t o t h e RPV.

A d d i t i o n a l a c t i o n s a r e r e q u i r e d t o minimize any p o t e n t i a l f i s s i o n product r e l e a s e t o t h e environment. This i n c l u d e s

( continued 1 GRAND GULF B 3.9-27 LDC 07019

RHR - High W a t e r L e v e l 0 3.9.8 BASES ACTIONS R.1. 8 . 7 . 8.3. and 8.4 (continued) e n s u r i n g secondary containment i s OPERABLE, one standby gas I t r e a t m e n t subsystem i s OPERABLE, and secondary containment i s o l a t i o n c a p a b i l i t y ( i . e . , a t l e a s t one i s o l a t i o n v a l v e and a s s o c i a t e d i n s t r u m e n t a t i o n i n each a s s o c i a t e d p e n e t r a t i o n n o t i s o l a t e d t h a t i s assumed t o be i s o l a t e d t o m i t i g a t e r a d i o a c t i v i t y re1 eases a r e OPERABLE or o t h e r a c c e p t a b l e a d m i n i s t r a t i v e c o n t r o l s t o assure i s o l a t i o n c a p a b i l i t y ) .

T h i s may be performed as an a d m i n i s t r a t i v e check, by examining l o g s o r o t h e r i n f o r m a t i o n , t o determine whether t h e components a r e o u t o f s e r v i c e f o r maintenance o r o t h e r reasons. I t i s n o t necessary t o p e r f o r m t h e S u r v e i l l a n c e s needed t o demonstrate t h e OPERABILITY o f t h e components.

I f , however, any r e q u i r e d component i s i n o p e r a b l e , t h e n i t must be r e s t o r e d t o OPERABLE s t a t u s . I n t h i s case, a s u r v e i l l a n c e may need t o be performed t o r e s t o r e t h e component t o OPERABLE s t a t u s . A c t i o n s must c o n t i n u e u n t i l a l l r e q u i r e d components a r e OPERABLE.

I f no decay heat removal subsystem (RHR shutdown c o o l i n g subsystem o r ADHRS) i s i n o p e r a t i o n , an a l t e r n a t e method of c o o l a n t c i r c u l a t i o n i s r e q u i r e d t o be e s t a b l i s h e d w i t h i n 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Completion Time i s m o d i f i e d such t h a t 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> i s a p p l i c a b l e s e p a r a t e l y f o r each occurrence i n v o l v i n g a l o s s o f coolant c i r c u l a t i o n .

D u r i n g t h e p e r i o d when t h e r e a c t o r c o o l a n t i s b e i n g c i r c u l a t e d by an a l t e r n a t e method ( o t h e r than by t h e r e q u i r e d RHR shutdown c o o l i n g subsystem o r ADHRS), t h e r e a c t o r c o o l a n t temperature must be p e r i o d i c a l l y monitored t o ensure proper f u n c t i o n i n g of t h e a l t e r n a t e method. The once p e r hour Completion Time i s deemed a p p r o p r i a t e .

SURVEILLANCE sL32M.J REQUIREMENTS T h i s S u r v e i l l a n c e demonstrates t h a t t h e RHR shutdown c o o l i n g subsystem o r ADHRS i s i n o p e r a t i o n and c i r c u l a t i n g r e a c t o r c o o l a n t . The r e q u i r e d f l o w r a t e i s determined by t h e f l o w r a t e necessary t o p r o v i d e s u f f i c i e n t decay heat removal c a p a b i l i t y . The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i s GRAND GULF 6 3.9-28 LDC 07019

RHR - H i g h Water Level 8 3.9.8 BASES SURVEILLANCE REQUIREMENTS (continued) s u f f i c i e n t i n view o f o t h e r v i s u a l and a u d i b l e i n d i c a t i o n s a v a i l a b l e t o t h e o p e r a t o r f o r m o n i t o r i n g t h e RHR subsystem i n t h e c o n t r o l room.

i REFERENCES AECM-90/0135, MAEC-90/0236, ER-GG-2007-0028 I GRAND GULF B 3.9-28a LDC 07029 I

RHR - Low Water Level B 3.9.9 B 3.9 REFUELING OPERATIONS B 3.9.9 Residual Heat Removal (RHR)-Low Water Level BASES BACKGROUND The purpose o f t h e RHR System i n MODE 5 i s t o remove decay h e a t and s e n s i b l e heat from t h e reactor coolant, as required by GDC 34. Each o f t h e two shutdown c o o l i n g loops o f t h e RHR System i s designed t o m a i n t a i n t h e r e a c t o r c o o l a n t b u l k average temperature as r e q u i r e d . Each l o o p c o n s i s t s o f one I motor d r i v e n pump, two heat exchangers, and a s s o c i a t e d p i p i n g and valves. Both loops have a common s u c t i o n from t h e same r e c i r c u l a t i o n l o o p . Each pump discharges t h e r e a c t o r c o o l a n t , a f t e r i t has been cooled by c i r c u l a t i o n through t h e r e s p e c t i v e h e a t exchangers, t o t h e r e a c t o r v i a separate feedwater l i n e s , t o t h e upper containment pool v i a a common s i n g l e f l o w d i s t r i b u t i o n sparger, o r t o t h e r e a c t o r v i a t h e l o w pressure c o o l a n t i n j e c t i o n p a t h . The RHR heat exchangers t r a n s f e r heat t o t h e Standby S e r v i c e Water System. The RHR shutdown c o o l i n g mode i s manually c o n t r o l 1ed .

An A l t e r n a t e Decay H e a t Removal System (ADHRS) i s a l s o a v a i l a b l e t o p r o v i d e t h e required decay h e a t removal. The ADHRS p r o v i d e s a s i n g l e subsystem c o n s i s t i n g o f two motor d r i v e n pumps, two heat exchangers, and a s s o c i a t e d p i p i n g and valves. The system u t i l i z e s t h e common RHR shutdown c o o l i n g s u c t i o n l i n e and some f u e l pool c o o l i n g and cleanup p i p i n g .

The system i s n o t s a f e t y - r e l a t e d and cannot be powered from an o n s i t e d i e s e l generator. The ADHRS heat exchangers t r a n s f e r heat t o t h e P l a n t S e r v i c e Water System (PSW). The ADHRS i s manually c o n t r o l l e d and i s o l a t e d from t h e common p o r t i o n s of t h e o t h e r systems.

APPLICABLE With t h e u n i t i n MODE 5, n e i t h e r t h e RHR System n o r t h e SAFETY ANALYSES ADHRS i s r e q u i r e d t o m i t i g a t e any events o r a c c i d e n t s evaluated i n t h e safety analyses. The RHR System, o r t h e ADHRS, i s r e q u i r e d f o r removing decay heat t o m a i n t a i n t h e temperature o f t h e r e a c t o r c o o l a n t .

Although t h e RHR System does n o t meet a s p e c i f i c c r i t e r i o n o f t h e NRC P o l i c y Statement, i t was i d e n t i f i e d i n t h e NRC P o l i c y Statement as an i m p o r t a n t c o n t r i b u t o r t o r i s k r e d u c t i o n . Therefore, t h e RHR System i s r e t a i n e d as a (continue0 GRAND GULF 6 3.9-29 LDC 07019

R H R - Low Water Level B 3.9.9 BASES APPLICABLE S p e c i f i c a t i o n . The ADHRS i s i n c l u d e d i n t h e S p e c i f i c a t i o n SAFETY ANALYSES t o p r o v i d e r e q u i r e m e n t s f o r decay heat removal c a p a b i l i t y (continued) d u r i n g an outage w h i l e t h e RHR System i s o u t o f s e r v i c e .

LCO I n MODE 5 w i t h i r r a d i a t e d f u e l i n t h e r e a c t o r p r e s s u r e vessel (RPW) and t h e water l e v e l c 22 f t 8 i n c h e s above t h e RPV f l a n g e b o t h RHR shutdown c o o l i n g subsystems must be OPERABLE, o r t h e ADHRS may be s u b s t i t u t e d f o r one o f t h e RHR subsystems.

The c u r r e n t r e q u i r e m e n t s f o r decay h e a t removal a r e : In MODE 5 w i t h no i n t e r f a c e between vessel b u l k c o o l a n t and spent f u e l p o o l , t h e requirement i s S 155°F.

I n MODE 5 w i t h vessel b u l k c o o l a n t i n t e r f a c i n g w i t h t h e spent f u e l p o o l , t h e requirement i s I; 140F.

An OPERABLE RHR shutdown c o o l i n g subsystem c o n s i s t s of an RHR pump, two h e a t exchangers, v a l v e s , p i p i n g , instruments, and c o n t r o l s t o ensure an OPERABLE f l o w p a t h . An OPERABLE ADHRS c o n s i s t s o f two pumps, two h e a t exchangers, valves, p i p i n g , i n s t r u m e n t s and c o n t r o l s t o ensure an OPERABLE flow p a t h . A t l e a s t one o f t h e r e q u i r e d RHR shutdown c o o l i n g subsystems must have a OPERABLE d i e s e l g e n e r a t o r capable of s u p p l y i n g e l e c t r i c a l power.

A d d i t i o n a l l y , each RHR shutdown c o o l i n g subsystem i s considered OPERABLE i f i t can be manually a l i g n e d (remote o r l o c a l ) i n t h e shutdown c o o l i n g mode f o r removal of decay heat. O p e r a t i o n ( e i t h e r continuous o r i n t e r m i t t e n t ) of one decay h e a t removal subsystem ( e i t h e r RHR o r ADHRS) can m a i n t a i n and reduce t h e r e a c t o r c o o l a n t temperature as r e q u i r e d . However, t o ensure adequate c o r e f l o w t o a l l o w f o r a c c u r a t e average r e a c t o r c o o l a n t temperature m o n i t o r i n g ,

n e a r l y c o n t i n u o u s o p e r a t i o n i s r e q u i r e d . A Note i s provided t o a l l o w a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> e x c e p t i o n f o r t h e o p e r a t i n g subsystem t o n o t be i n o p e r a t i o n every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

APPLICABILITY Two decay h e a t removal subsystems a r e r e q u i r e d t o be OPERABLE i n MODE 5, w i t h i r r a d i a t e d f u e l i n t h e RPV and t h e water l e v e l c 22 f t 8 i n c h e s above t h e t o p o f t h e RPV f l a n g e , t o p r o v i d e decay heat removal. RHR System requirements i n o t h e r MODES a r e covered by LCOs i n S e c t i o n 3.4, Reactor Coolant System (RCS); S e c t i o n 3.5, (continued)

GRAND G U L F B 3.9-30 LDC 07019

RHR - Low Water Level B 3.9.9 BASES APPLICABILITY (continued)

Emergency Core C o o l i n g Systems ( E C C S ) and Reactor Core I s o l a t i o n C o o l i n g ( R C I C ) System; and S e c t i o n 3.6, I

Containment Systems. RHR Shutdown C o o l i n g System requirements i n MODE 5, w i t h t h e water l e v e l 2 22 f t 8 i n c h e s above t h e RPV f l a n g e , a r e g i v e n i n LCO 3.9.8, "Residual Heat Removal (RHR) - H i g h Water Level .*I (continued)

GRAND GULF B 3.9-30a LDC 07019 I

RHR - Low Water Level B 3.9.9 BASES (continued)

SURVEILLANCE sfLuLu REQUIREMENTS T h i s S u r v e i l l a n c e demonstrates that one RHR shutdown c o o l i n g subsystem o r ADHRS i s i n o p e r a t i o n and c i r c u l a t i n g r e a c t o r c o o l a n t . The r e q u i r e d f l o w r a t e i s determined by t h e f l o w r a t e necessary t o p r o v i d e s u f f i c i e n t decay heat removal c a p a b i l i t y . The Frequency o f 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i s s u f f i c i e n t i n view o f o t h e r v i s u a l and a u d i b l e i n d i c a t i o n s a v a i l a b l e t o t h e o p e r a t o r f o r m o n i t o r i n g t h e RHR subsystem i n t h e c o n t r o l room.

REFERENCES AECM-90/0135, MAEC-90/0236, ER-GG-2007-0028. I GRAND G U L F 0 3.9-33 LDC 07019

I n s e r v i c e Leak and H y d r o s t a t i c T e s t i n g O p e r a t i o n B 3.10.1 B 3.10 SPECIAL OPERATIONS B 3.10.1 I n s e r v i c e Leak and H y d r o s t a t i c T e s t i n g Operation BASES

~- ~~

BAC KGROUNO The purpose o f t h i s Special Operations LCO i s t o alloH c e r t a i n r e a c t o r c o o l a n t pressure t e s t s t o be performed i n MODE 4 when t h e m e t a l l u r g i c a l c h a r a c t e r i s t i c s o f t h e r e a c t o r p r e s s u r e vessel (RPV) r e q u i r e t h e p r e s s u r e t e s t i n g a t temperatures > 200°F ( n o r m a l l y corresponding t o MODE 3 ) o r t o a l l o w c o m p l e t i n g these r e a c t o r c o o l a n t pressure t e s t s when t h e i n i t i a l c o n d i t i o n s do n o t r e q u i r e temperatures >

200°F. Furthermore, t h e purpose i s t o a l l o w continued performance o f c o n t r o l r o d scram t i m e t e s t i n g r e q u i r e d by SR 3.1.4.1 o r SR 3.1.4.4 i f r e a c t o r c o o l a n t temperatures exceed 200°F when t h e c o n t r o l r o d scram t i m e t e s t i n g i s i n i t i a t e d i n c o n j u n c t i o n w i t h an i n s e r v i c e l e a k o r h y d r o s t a t i c t e s t .

These c o n t r o l r o d scram t i m e t e s t s would be performed i n accordance w i t h LCO 3.10.4, " S i n g l e C o n t r o l Rod Withdrawal -

Cold Shutdown," d u r i n g MOOE 4 o p e r a t i o n .

I n s e r v i c e h y d r o s t a t i c t e s t i n g and system leakage p r e s s u r e t e s t s requlred by Sectton X I o f the American Society o f Mechanical Engineers (ASME) B o i l e r and Pressure Vessel Code

( R e f . 1) a r e performed p r i o r t o t h e r e a c t o r going c r i t i c a l a f t e r a r e f u e l i n g outage. R e c i r c u l a t i o n pump o p e r a t i o n and a water s o l i d RPV (except f o r an a i r bubble f o r pressure c o n t r o l ) a r e used t o achieve t h e necessary temperatures and pressures r e q u i r e d f o r t h e s e t e s t s . The minimum temperatures ( a t t h e r e q u i r e d p r e s s u r e s ) allowed f o r these t e s t s a r e determined from t h e RPV p r e s s u r e and temperature

( P / T ) l i m i t s r e q u f r e d by LCO 3.4.11, "Reactor Coolant System

( R C S ) Pressure and Temperature ( P I T ) L i m i t s . " These l i m i t s a r e c o n s e r v a t i v e l y based on t h e f r a c t u r e toughness o f t h e r e a c t o r vessel, t a k i n g i n t o account a n t i c i p a t e d vessel n e u t r o n f 1uence .

With increased r e a c t o r vessel f l u e n c e o v e r t i m e , t h e minimum a l l o w a b l e vessel temperature increases a t a g i v e n pressure.

P e r i o d i c u p d a t e s t o the RCS P I T limit curves are performed a s necessary, based on t h e r e s u l t s o f analyses o f i r r a d i a t e d s u r v e i l l a n c e specimens removed from t h e vessel. H y d r o s t a t i c and l e a k t e s t i n g w i l l e v e n t u a l l y be r e q u i r e d w i t h minimum r e a c t o r c o o l a n t temperatures > 200°F. However, even w i t h r e q u i r e d minimum r e a c t o r c o o l a n t temperatures < ZOOOF, I GRAND GULF B 3.10-1 LDC 07008

I n s e r v i c e Leak and H y d r o s t a t i c T e s t i n g Operation B 3.10.1 BASES BACKGROUND m a i n t a i n i n g RCS temperatures w i t h i n a s m a l l band d u r i n g the (continued) t e s t can be i m p r a c t i c a l . Removal o f h e a t a d d i t i o n f r o m r e c i r c u l a t i o n pump o p e r a t i o n and r e a c t o r c o r e decay heat i s c o a r s e l y c o n t r o l l e d b y c o n t r o l rod d r i v e h y d r a u l i c system f l o w and r e a c t o r w a t e r cleanup system n o n - r e g e n e r a t i v e heat exchanger o p e r a t i o n . Test c o n d i t i o n s a r e focused on m a i n t a i n i n g a steady s t a t e pressure, and t i g h t l y l i m i t e d temperature c o n t r o l poses an unnecessary burden on t h e o p e r a t o r and may n o t be a c h i e v a b l e i n c e r t a i n i n s t a n c e s .

Scram t i m e t e s t i n g r e q u i r e d by SR 3.1.4.1 and SR 3.1.4.4 r e q u i r e s r e a c t o r steam dome pressure 950 p s i g . The h y d r o s t a t i c and/or RCS leakage t e s t s r e q u i r e p r e s s u r e o f a p p r o x i m a t e l y 1,000 p s i g .

Other t e s t i n g may be performed i n c o n j u n c t i o n w i t h t h e allowances f o r i n s e r v i c e l e a k or h y d r o s t a t i c t e s t s and c o n t r o l rod scram t i m e t e s t s .

APPLICABLE A l l o w i n g t h e r e a c t o r t o be considered i n MODE 4 when t h e SAFETY ANALYSES r e a c t o r c o o l a n t temperature i s > ZOOOF, d u r i n g o r as a consequence o f , h y d r o s t a t i c o r l e a k t e s t i n g , o r as a consequence o f c o n t r o l rod scram t i m e t e s t i n g i n i t i a t e d i n c o n j u n c t i o n w i t h an i n s e r v i c e l e a k o r h y d r o s t a t i c t e s t ,

e f f e c t i v e l y p r o v i d e s an e x c e p t i o n t o MODE 3 requirements, i n c l u d i n g OPERABILITY o f p r i m a r y containment and t h e f u l l complement o f redundant Emergency Core C o o l i n g Systems (ECCS). Since t h e h y d r o s t a t i c o r l e a k t e s t s a r e performed n e a r l y w a t e r s o l i d , a t l o w decay heat values, and near MODE 4 c o n d i t i o n s , t h e s t o r e d energy i n t h e r e a c t o r core w i l l be v e r y low. Under these c o n d i t i o n s , t h e p o t e n t i a l f o r f a i l e d f u e l and a subsequent i n c r e a s e i n (continuedl GRAND GULF B 3.10-la LDC 07008 1

I n s e r v i c e Leak and H y d r o s t a t i c T e s t i n g O p e r a t i o n B 3.10.1 BASES LCO > ZOOOF, w h i l e t h e ASME i n s e r v i c e t e s t i t s e l f r e q u i r e s the (continued) s a f e t y / r e l i e f v a l v e s t o be gagged, p r e v e n t i n g t h e i r OPERABILITY. A d d i t i o n a l l y , even w i t h r e q u i r e d minimum r e a c t o r c o o l a n t temperatures < ZOOOF, RCS temperatures may d r i f t above 200°F d u r i n g t h e performance of i n s e r v i c e l e a k and h y d r o s t a t i c t e s t i n g o r d u r i n g subsequent c o n t r o l r o d scram t i m e t e s t i n g , which i s t y p i c a l l y performed i n c o n j u n c t i o n w i t h i n s e r v i c e l e a k and h y d r o s t a t i c t e s t i n g .

While t h i s S p e c i a l O p e r a t i o n s LCO i s p r o v i d e d f o r i n s e r v i c e l e a k and h y d r o s t a t i c t e s t i n g , and f o r scram t i m e t e s t i n g i n i t i a t e d i n c o n j u n c t i o n w i t h an i n s e r v i c e l e a k o r h y d r o s t a t i c t e s t , p a r a l l e l performance o f o t h e r t e s t s and i n s p e c t i o n s i s n o t precluded.

I f i t i s d e s i r e d t o p e r f o r m these t e s t s w h i l e complying w i t h t h i s S p e c i a l O p e r a t i o n s LCO, t h e n t h e MODE 4 a p p l i c a b l e LCOs and s p e c i f i e d MODE 3 LCOs must be met. T h i s S p e c i a l O p e r a t i o n s LCO a l l o w s changing T a b l e 1.1-1 temperature l i m i t s f o r MODE 4 t o "NA" and suspending t h e requirements o f LCO 3.4.10, "Residual Heat Removal (RHR) Shutdown C o o l i n g System-Cold Shutdown." The a d d i t i o n a l requirements f o r secondary containment LCOs t o be met w i l l p r o v i d e s u f f i c i e n t p r o t e c t i o n f o r o p e r a t i o n s a t r e a c t o r c o o l a n t temperatures

=. 200°F f o r t h e purposes o f p e r f o r m i n g an i n s e r v i c e l e a k o r h y d r o s t a t i c t e s t , and f o r c o n t r o l r o d scram t i m e t e s t i n g i n i t i a t e d i n c o n j u n c t i o n w i t h an i n s e r v i c e l e a k o r hydrostatic test.

T h i s LCO a l l o w s p r i m a r y containment t o be open f o r f r e q u e n t u n o b s t r u c t e d access t o perform i n s p e c t i o n s , and f o r outage a c t i v i t i e s on v a r i o u s systems t o c o n t i n u e c o n s i s t e n t w i t h t h e MODE 4 a p p l i c a b l e requirements t h a t a r e i n e f f e c t immediately p r i o r t o and i m m e d i a t e l y a f t e r t h i s o p e r a t i o n .

APPLICABILITY The MODE 4 requirements may o n l y be m o d i f i e d f o r t h e performance o f , o r as a consequence o f , i n s e r v i c e l e a k o r h y d r o s t a t i c t e s t s o r as a consequence of c o n t r o l rod scram t i m e t e s t i n g i n i t i a t e d i n c o n j u n c t i o n w i t h an i n s e r v i c e l e a k o r h y d r o s t a t i c t e s t , so t h a t t h e s e o p e r a t i o n s can be considered as i n MODE 4 , even though t h e r e a c t o r c o o l a n t temperature i s > 200°F. The a d d i t i o n a l requirement f o r (continued)

GRAND GULF B 3.10-3 LDC 07008

I n s e r v i c e Leak and H y d r o s t a t i c T e s t i n g Operation B 3.10.1 BASES I

I APPLICABILITY secondary containment OPERABILITY a c c o r d i n g t o the imposed

( cont inued 1 MODE 3 requirements p r o v i d e s c o n s e r v a t i s m i n t h e response of t h e u n i t t o any event t h a t may o c c u r . Operations i n a l l o t h e r MODES a r e u n a f f e c t e d by t h i s LCO.

ACTIONS A Note has been p r o v i d e d t o modify t h e ACTIONS r e l a t e d t o i n s e r v i c e l e a k and h y d r o s t a t i c t e s t i n g o p e r a t i o n .

S e c t i o n 1.3, Completion Times, s p e c i f i e s once a C o n d i t i o n has been e n t e r e d , subsequent d i v i s i o n s , subsystems, components, o r v a r i a b l e s expressed i n t h e C o n d i t i o n d i s c o v e r e d t o be i n o p e r a b l e or n o t w i t h l n l i m i t s , w i l l not r e s u l t i n s e p a r a t e e n t r y i n t o t h e C o n d i t i o n . S e c t i o n 1.3 a l s o s p e c i f i e s t h a t Required A c t i o n s o f t h e C o n d i t i o n c o n t i n u e t o a p p l y f o r each a d d i t i o n a l f a i l u r e , w i t h Completion Times based on i n i t i a l e n t r y i n t o t h e C o n d i t i o n .

However, t h e Required A c t i o n s f o r each requirement o f t h e LCO n o t met p r o v i d e a p p r o p r i a t e compensatory measures f o r

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GRAND G U L F B 3.10-3a LDC 07008 1

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