GNRO-2007/00021, Technical Specification Bases, Technical Requirements Manual and Core Operating Limits Updates to the NRC for Period Dated April 7, 2007

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Technical Specification Bases, Technical Requirements Manual and Core Operating Limits Updates to the NRC for Period Dated April 7, 2007
ML071070209
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 04/11/2007
From: Bottemiller C
Entergy Operations
To:
Document Control Desk, NRC/NRR/ADRO
References
GNRO-2007/00021
Download: ML071070209 (25)
v • d • e


Text

Entergy Operations, Inc.

Waterloo Road P.O. Box 756 Port Gibson, MS 39150 Tel 601 437 6299 Charles A. Bottemiller Manager Plant Licensing GNRO-2007/00021 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Technical Specification Bases, Technical Requirements Manual and Core Operating Limits Updates to the NRC for Period Dated April 7, 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 and Technical Requirements Manual (TRM) Section 1.04, Entergy Operations, Inc. hereby submits an update of all changes made to GGNS Technical Specification Bases since the last submittal (GNRO-2007/00019 dated March 30, 2007 and TRM since the last submittal (GNRO-2007/00017) letter dated March 1, 2007 to the NRC from GGNS. Also included is the latest revision to the Core Operating Limits Report for Cycle 16. 'hese updates are consistent with update frequency listed in 10CFR50.71(e).

This letter d o e s not contain any commitments.

Should you have any questions, please contact James Owens at (60 ) 437-6219.

Yours truly, CAB/JEO attachments: 1. Technical Specification Bases

2. Technical Requirement Manual Page
3. Core Operating Limits Report cc: (See Next Page)

GNRO-2007/0002I Page 2 cc:

NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ALL LETTERS Arlington, TX 76011-4005 U S . Nuclear Regulatory

- Commission ALL LETTERS -

ATTN: Mr. Bhalchandra Vaidya, NRR/DORL (w/2) COURIER DELIVERY (FEDEX, ETC.)

ATTN: ADDRESSEE ONLY ADDRESS ONLY -

ATTN: Courier Delivery Only **"DO NOT USE FOR Mail Stop OWFN/O-7DIA U.S. POSTAL 11555 Rockville Pike SERVlCE Rockville, MD 20852-2378 ADDRESS***"

NOT USED IF EIE USED

ATTACHMENT I to GNRO-2007/00021 Grand Gulf Technical Specification Bases Pages

LCO Appl icab! 1 it y B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES

~

LCOS LCO 3.0.1 t h r o u g h LCO 3.0.8 e s t a b l i s h t h e g e n e r a l I r e q u i r e m e n t s a p p l i c a b l e t o a l l S p e c i f i c a t i o n s and a p p l y a t a1 1 t i m e s , u n l e s s o t h e r w i s e s t a t e d .

LCO 3.0.1 LCO 3.0.1 e s t a b l i s h e s t h e A p p l i c a b i l i t y s t a t e m e n t w i t h i n each i n d i v i d u a l S p e c i f i c a t i o n as t h e r e q u i r e m e n t f o r when t h e LCO i s r e q u i r e d t o be met ( i . e . , when t h e u n i t i s i n t h e MODES o r o t h e r s p e c i f i e d c o n d i t i o n s o f t h e A p p l i c a b i l i t y s t a t e m e n t o f each S p e c i f i c a t i o n ) .

LCO 3.0.2 LCO 3.0.2 e s t a b l i s h e s t h a t upon d i s c o v e r y o f a f a i l u r e t o meet an LCO, t h e a s s o c i a t e d A C T I O N S s h a l l be met. The C o m p l e t i o n Time o f each R e q u i r e d A c t i o n f o r an A C T I O N S C o n d i t i o n i s a p p l i c a b l e f r o m t h e p o i n t i n t i m e t h a t an ACTIONS C o n d i t i o n i s e n t e r e d . The R e q u i r e d A c t i o n s e s t a b l i s h t h o s e r e m e d i a l measures t h a t must be t a k e n w i t h i n s p e c i f i e d C o m p l e t i o n Times when t h e r e q u i r e m e n t s o f an LCO a r e n o t met. T h i s S p e c i f i c a t i o n e s t a b l i s h e s t h a t :

a. Completion o f t h e Required Actions w i t h i n t h e s p e c i f i e d C o m p l e t i o n Times c o n s t i t u t e s c o m p l i a n c e w i t h a S p e c i f i c a t i o n ; and
b. Completion o f t h e Required Actions i s n o t r e q u i r e d when an LCO i s met w i t h i n t h e s p e c i f i e d C o m p l e t i o n Time, u n l e s s o t h e r w i s e s p e c i f i e d .

There a r e two b a s i c t y p e s o f R e q u i r e d A c t i o n s . The f i r s t t y p e o f Required A c t i o n s p e c i f i e s a t i m e l i m i t i n which t h e LCO must be met. T h i s t i m e l i m i t i s t h e C o m p l e t i o n Time t o r e s t o r e an i n o p e r a b l e system o r component t o OPERABLE s t a t u s or t o restore variables t o within specified l i m i t s . I f t h i s t y p e o f R e q u i r e d A c t i o n i s n o t completed w i t h i n t h e s p e c i f i e d C o m p l e t i o n Time, a shutdown may be r e q u i r e d t o p l a c e t h e u n i t i n a MODE o r c o n d i t i o n i n w h i c h t h e S p e c i f i c a t i o n i s n o t a p p l i c a b l e . (Whether s t a t e d as a Required A c t i o n o r n o t , c o r r e c t i o n o f t h e entered Condition i s an a c t i o n t h a t may always be c o n s i d e r e d upon e n t e r i n g ACTIONS.) The second t y p e o f R e q u i r e d A c t i o n s p e c i f i e s t h e r e m e d i a l measures t h a t p e r m i t c o n t i n u e d o p e r a t i o n o f t h e GRAND GULF B 3.0-1 LDC 07010

LCO A p p l i c a b i l i t y B 3.0 BASES LCO 3.0.6 e x i s t s , t h e a p p r o p r i a t e C o n d i t i o n s and Required A c t i o n s o f

( c o n t i nued 1 t h e LCO i n which t h e l o s s o f s a f e t y f u n c t i o n e x i s t s a r e r e q u i r e d t o be e n t e r e d .

LCO 3.0.7 There a r e c e r t a i n s p e c i a l t e s t s and o p e r a t i o n s r e q u i r e d t o be performed a t v a r i o u s t i m e s over t h e l i f e o f t h e u n i t .

These s p e c i a l t e s t s and o p e r a t i o n s a r e necessary t o demonstrate s e l e c t u n i t performance c h a r a c t e r i s t i c s , t o p e r f o r m s p e c i a l maintenance a c t i v i t i e s , and t o p e r f o r m s p e c i a l e v o l u t i o n s . S p e c i a l O p e r a t i o n s LCOs i n S e c t i o n 3.10 a l l o w s p e c i f i e d TS requirements t o be changed t o p e r m i t performances o f t h e s e s p e c i a l t e s t s and o p e r a t i o n s , which o t h e r w i s e c o u l d n o t be performed if r e q u i r e d t o comply w i t h t h e requirements o f these TS. Unless o t h e r w i s e s p e c i f i e d ,

a l l t h e o t h e r TS requirements remain unchanged. T h i s w i l l ensure a l l a p p r o p r i a t e requirements o f t h e MODE o r o t h e r s p e c i f i e d condition not d i r e c t l y associated w i t h o r required t o be changed t o p e r f o r m t h e s p e c i a l t e s t o r o p e r a t i o n w i l l remain i n e f f e c t .

The A p p l i c a b i l i t y o f a Special O p e r a t i o n s LCO r e p r e s e n t s a c o n d i t i o n n o t n e c e s s a r i l y i n compliance w i t h t h e normal r e q u i r e m e n t s o f t h e TS. Compliance w i t h Special O p e r a t i o n s LCOs i s o p t i o n a l . A s p e c i a l o p e r a t i o n may be performed e i t h e r under t h e p r o v i s i o n s of t h e a p p r o p r i a t e Special O p e r a t i o n s LCO o r under t h e o t h e r a p p l i c a b l e TS requirements. I f i t i s desired t o perform the special o p e r a t i o n under t h e p r o v i s i o n s o f t h e S p e c i a l Operations LCO, t h e requirements o f t h e S p e c i a l Operations LCO s h a l l be f 01 owed. When a Special O p e r a t i o n s LCO r e q u i r e s another LCO t o be met, o n l y t h e requirements o f t h e LCO statement a r e r e q u i r e d t o be met r e g a r d l e s s of t h a t LCO's APP i c a b i l i t y ( i . e . , should t h e requirements o f t h i s o t h e r LCO n o t be met, t h e ACTIONS of t h e S p e c i a l Operations LCO a PP y , n o t t h e ACTIONS o f t h e o t h e r LCO). However, t h e r e a r e i n s t a n c e s where t h e S p e c i a l O p e r a t i o n s LCO's ACTIONS may d i r e c t t h e o t h e r LCO's ACTIONS be met. The S u r v e i l l a n c e s o f t h e o t h e r LCO a r e n o t r e q u i r e d t o be met, unless s p e c i f i e d i n t h e S p e c i a l Operations LCO. I f c o n d i t i o n s e x i s t such t h a t t h e A p p l i c a b i l i t y of any o t h e r LCO i s met, a l l the o t h e r LCO's requirements ( A C T I O N S and S R s ) a r e r e q u i r e d t o be met c o n c u r r e n t w i t h t h e requirements of t h e Special O p e r a t i o n s LCO.

( c o n t inued ) I GRAND GULF B 3.0-9 LDC 07010

LCO Appl ic a b i 1 it y B 3.0 BASES (continued) I LCO 3.0.8 LCO 3.0.8 e s t a b l i s h e s c o n d i t i o n s under which systems a r e considered t o remain capable o f p e r f o r m i n g t h e i r i n t e n d e d s a f e t y f u n c t i o n when a s s o c i a t e d snubbers a r e n o t capable o f p r o v i d i n g t h e i r a s s o c i a t e d support f u n c t i o n ( s ) . This LCO s t a t e s t h a t t h e supported system i s n o t considered t o be i n o p e r a b l e s o l e l y due t o one o r more snubbers n o t capable o f p e r f o r m i n g t h e i r a s s o c i a t e d support f u n c t i o n ( s 1 . T h i s i s a p p r o p r i a t e because a l i m i t e d l e n g t h o f t i m e i s a l l o w e d f o r maintenance, t e s t i n g , o r r e p a i r o f one or more snubbers n o t capable o f p e r f o r m i n g t h e i r a s s o c i a t e d support f u n c t i o n ( s )

and a p p r o p r i a t e compensatory measures a r e s p e c i f i e d i n t h e snubber requirements, which a r e l o c s t e d o u t s i d e o f t h e Technical S p e c i f i c a t i o n s ( T S ) under 1 icensee c o n t r o l . The snubber requirements do n o t meet t h e c r i t e r i a i n 10 CFR 5 0 . 3 6 ( c ) ( Z > ( i i ) , and, as such, a r e a p p r o p r i a t e f o r c o n t r o l by t h e l i c e n s e e .

I f t h e a l l o w e d t i m e e x p i r e s and t h e snubber(s1 a r e unable t o p e r f o r m t h e i r a s s o c i a t e d support f u n c t i o n ( s 1 , t h e a f f e c t e d supported systems LCO(s1 must be d e c l a r e d n o t m e t and t h e C o n d i t i o n s and Required A c t i o n s e n t e r e d i n accordance w i t h LCO 3.0.2.

LCO 3.0.8.a a p p l i e s when one o r more snubbers a r e n o t capable o f p r o v i d i n g t h e i r a s s o c i a t e d support f u n c t i o n ( s 1 t o a s i n g l e t r a i n o r subsystem o f a m u l t i p l e t r a i n o r subsystem supported system o r t o a s i n g l e t r a i n o r subsystem supported system. LCO 3.0.8.a a l l o w s 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> t o r e s t o r e t h e snubber(s1 b e f o r e d e c l a r i n g t h e supported system i n o p e r a b l e .

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time i s reasonable based on t h e l o w p r o b a b i l i t y o f a seismic event c o n c u r r e n t w i t h an event t h a t would r e q u i r e o p e r a t i o n o f t h e supported system o c c u r r i n g w h i l e t h e snubber(s1 a r e n o t capable o f p e r f o r m i n g t h e i r a s s o c i a t e d support f u n c t i o n and due t o t h e a v a i l a b i l i t y o f t h e redundant t r a i n o f t h e supported system.

LCO 3.0.8.b a p p l i e s when one o r more snubbers a r e n o t capable o f p r o v i d i n g t h e i r a s s o c i a t e d f u n c t i o n ( s 1 t o more t h a n one t r a i n o r subsystem o f a m u l t i p l e t r a i n o r subsystem supported system. LCO 3.0.8.b a l l o w s 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> t o r e s t o r e t h e snubber(s1 b e f o r e d e c l a r i n g t h e supported system i n o p e r a b l e . The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Completion Time i s reasonable based on t h e low p r o b a b i l i t y o f a s e i s m i c event concurrent w i t h an (continued)

GRAND GULF 6 3.0-9a LDC 07010 I

LCO A p p l i c a b i l i t y B 3.0 BASES LCO 3.0.8 e v e n t t h a t w o u l d r e q u i r e o p e r a t i o n o f t h e s u p p o r t e d system

( c o n t i nued 1 o c c u r r i n g w h i l e t h e snubber(s1 a r e n o t capable o f performing t h e i r associated support function.

LCO 3.0.8 r e q u i r e s t h a t r i s k be assessed and managed.

I n d u s t r y and NRC g u i d a n c e on t h e i m p l e m e n t a t i o n o f 10 CFR 5 0 . 6 5 ( a ) ( 4 ) ( t h e Maintenance R u l e ) does n o t a d d r e s s s e i s m i c r i s k . However, use o f LCO 3.0.8 s h o u l d be c o n s i d e r e d w i t h r e s p e c t t o o t h e r p l a n t m a i n t e n a n c e a c t i v i t i e s , and i n t e g r a t e d i n t o t h e e x i s t i n g Maintenance Rule process t o t h e e x t e n t p o s s i b l e s o t h a t m a i n t e n a n c e on any u n a f f e c t e d t r a i n o r subsystem i s p r o p e r l y c o n t r o l l e d , and emergent i s s u e s a r e p r o p e r l y addressed. The r i s k assessment need n o t be q u a n t i f i e d , b u t a q u a l i t a t i v e awareness o f t h e v u l n e r a b i l i t y o f systems and components when one o r more snubbers a r e n o t able t o perform t h e i r associated support function.

GRAND GULF B 3.0-9b LDC 07010 I

ATTACHMENT 2 to GNRO-2007/00021 Grand Gulf Technical Requirement Manual

b. a determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

Shall become effective upon review and acceptance by the OSRC and the approval of the General Manager, Plant Operations.

7.6.3.9 pFFSITE DOSE CAGCVLATION MANUAL ( ODCM 1 Licensee initiated changes to the ODCM shall become effective upon review and acceptance by the OSRC.

7.6.3.10 SNUBBER P R W M 7.6.3.10.1 Deleted I 7.6.3.10.2 Deleted I 7.6 -3.10.3 Surveillance Requirements Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program in lieu of the requirements of Technical Specification 5.5.6 or TRM 7.6.3.3.

a. v As used in this program, "type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.

7-8 LDC 07010

Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 7.6.3.10-1.

The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 7.6.3.10-1 and the first inspection interval determined using these criteria shall be based upon the previous inspection interval as established by the requirements in effect before July 8, 1991.

C. Visual Inspection Accegtance Criteria Visual inspection shall verify that:

(1) the snubber has no visible indications or damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and the snubber anchorage are functional.

Snubbers which appear inoperable as a result of visual inspections shall be classified a8 unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that:

(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 7.6.3.10.3.f.

A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber.

If continued operation cannot be justified, the snubber shall be declared inoperable and the LCO 3.0.8 requirements I shall be met.

TRM 7-9 LDC 07010

3) For RF07 a one time deviation was taken to the Functional Testing described in 1) and 2) above f o r PSA 1/4 and 1/2 snubbers. In lieu of functionally testing a sample of P S A 1 / 4 and 1/2 snubbers, pfreedom of motion" testing was performed on 173 of 176 PSA 1/4 and 1/2 snubbers (the remaining 3 snubbers are RF06 failures and require functional testing). The snubbers tested using "freedom of motion" testing suspect of high drags are functionally tested.

To perform Functional Testing 60 days prior to a planned shutdown on a system that: is operable the following limitations must be applied.

a) The functional testing of snubbers on operable systems shall not start until 60 days before the planned outage.

b) Only one snubber can be removed from a stress problem at a time without further engineering review.

c) Snubbers adjacent to critical locations (equipment nozzles, large valves with motors) shall not be removed while the system is operable.

d) Snubbers on one train of multiple train systems shall not be removed while a snubber is removed from the other train.

Testing equipment failure during functional testing may invalidate that day's testing and allow that day's testing to resume anew at a later time, providing all snubbers tested with the failed eqyipment during the day of equipment failure are retested,. The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of size, and capacity of snubbers of each type. Snubbers placed in the same locations as snubbers which failed the previoucp functional test shall be retested at the time of the next functional test but shall not be included in the sample plan. If during the functional testing, additional sampling is required due to failure of only one type of snubber, the functional testing results shall be revierred at the time to determine if additional samples should be limited to the type of snubber which has failed the functional testing.

TRM 7-14 LDC 07010

ATTACHMENT 3 to GNRO-2007/00021 Grand Gulf Core Operating Limits Report

CORE OPERATING L I M I T S REPORT REASON FOR REVISION T h i s r e v i s i o n provides t h e Cycle 16 c o r e o p e r a t i n g l i m i t s . These l i m i t s a r e based on a core power o f 3898 MWt.

TABLE OF CONTENTS 1.o PURPOSE 3 2.0 SCOPE 3

3.0 REFERENCES

4-6 3.1 Background References 4 3.2 Current Cycle References 4 3.3 Methodology References 5-6 4.0 DEFINITIONS 7 5.0 GENERAL REQUIREMENTS 8 5.1 Average Planar L i n e a r Heat Generation Rates 8 5.2 Minimum C r i t i c a l Power R a t i o 8 5.3 L i n e a r Heat Generation Rate 8 5.4 S t a b i l i t y 8 5.5 A p p l i c a b i l i t y 8 Figure(s) 1 APLHGR Operating L i m i t s 9 Figure(s) 2 MCPR Operating L i m i t s 10-13 Figure(s) 3 LHGR Operating L i m i t s 14-15

, Figure(s) 4, E1A S t a b i l i t y L i m i t s I 16-20 .

COLR Page 2 LDC 07011

CORE OPERATING L I M I T S REPORT 1 .O PURPOSE On October 4, 1988, the NRC issued Generic L e t t e r 88-16 [ 3 . 1 . 1 ] encouraging licensees t o remove c y c l e - s p e c i f i c parameter l i m i t s from Technical S p e c i f i c a t i o n s and t o place these l i m i t s i n a f o r m a l r e p o r t t o be prepared by t h e licensee. As l o n g as t h e parameter l i m i t s were developed w i t h NRC-approved methodologies, t h e l e t t e r i n d i c a t e d t h a t t h i s would remove unnecessary burdens on licensee and NRC resources.

On October 29, 1992, Entergy Operations submitted a Proposed Amendment t o the Grand G u l f Operating License requesting changes t o t h e GGNS Technical S p e c i f i c a t i o n s t o remove c e r t a i n r e a c t o r physics parameter l i m i t s t h a t change each f u e l cycle

[3.1.2]. This amendment committed t o p l a c i n g these operating l i m i t s i n a separate Core Operating L i m i t s Report (COLR) which i s defined i n Technical S p e c i f i c a t i o n s .

T h i s PCOL was approved by the NRC by SER dated January 21, 1993 [ 3 . 1 . 3 ] .

The COLR i s c o n t r o l l e d as a License Basis Document and revised accordingly f o r each f u e l c y c l e o r remaining p o r t i o n o f a f u e l cycle. Any r e v i s i o n s t o t h e COLR must be submitted t o t h e NRC f o r i n f o r m a t i o n as required by Tech Spec 5.6.5 and tracked by LCTS 29132. This COLR r e p o r t s t h e Cycle 16 core operating and s t a b i l i t y l i m i t s . I 2.0 SCOPE As defined i n Technical S p e c i f i c a t i o n 1 . 1 , the COLR i s t h e GGNS document t h a t provides t h e core operating l i m i t s f o r t h e current f u e l cycle. This document i s prepared i n accordance w i t h Technical S p e c i f i c a t i o n 5.6.5 f o r each reload c y c l e using NRC-approved a n a l y t i c a l methods.

The Cycle 16 core operating and s t a b i l i t y l i m i t s included i n t h i s r e p o r t are: I t h e Average Planar Linear Heat Generation Rate (APLHGR),

t h e Minimum C r i t i c a l Power Ratio (MCPR) ( i n c l u d i n g EOC-RPT inoperable),

0 t h e L i n e a r Heat Generation Rate (LHGA) l i m i t , and 0 the E1A s t a b i l i t y l i m i t s .

COLR Page 3 LDC 07011

CORE OPERATING L I M I T S REPORT

3.0 REFERENCES

T h i s s e c t i o n c o n t a i n s t h e background, c y c l e - s p e c i f i c , and methodology references used i n t h e s a f e t y a n a l y s i s o f Grand Gulf Cycle 16.

3.1 Background References 3.1.1 MAEC-88/0313, Generic L e t t e r 88-16, Removal o f C y c l e - S p e c i f i c Parameter L i m i t s from Technical S p e c i f i c a t i o n s , October 4, 1988.

3.1.2 GNRO-92-00093, Proposed Amendment t o Grand G u l f Operating License, PCOL-92/07, dated October 29, 1992.

3.1.3 GNRI-93-0008, Amendment 106 t o Grand G u l f Operating License, January 21, 1993.

3.1.4 GEXI 2000-00116, K.V. Walters t o J.B. Lee, Technical S p e c i f i c a t i o n and COLR References f o r Grand Gulf Nuclear S t a t i o n and R i v e r Bend S t a t i o n ,

November 3, 2000.

3.2 Current Cycle References 3.2.1 ANP-2581 Revision 0, Grand G u l f Nuclear S t a t i o n Cvcle 16 Reload Analvsis, dated December 2006.

3.2.2 CEO 2000-00094, J i m Head t o M.D. Withrow, Revised E1A Related COLR I n p u t , dated A p r i l 20, 2000.

COLR Page 4 LDC 07011

CORE OPERATING LIMITS REPORT 3.3 Methodology References The T ec hni c al S p e c i f i c a t i o n s provided i n brac k ets .

(TS) supported by each methodology re ference a r e I

3.3.1 XN-NF-81-58(P)(A) R e v is io n 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response E v a lu a tio n Model, Exxon Nuclear Company, March 1984 [TS 3.2.1, TS 3.2.2, TS 3.2.31.

3.3.2 XN-NF-85-67(P)(A) R e v is io n 1, Generic Mechanical Design f o r Exxon Nuclear J e t Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986

[TS 3.2.31.

3.3.3 EMF-85-74(P) Rev i s i o n 0 Supplement 1 (P)(A) and Supplement 2 ( P)(A ),

c6RODEX2A (BWR) Fuel Rod Thermal-Mechanical E v a l u a t i o n Model, Siemens Power Corporati on, February 1998 [TS 3.2.31.

3.3.4 ANF-89-98(P)(A) Rev is io n 1 and Supplement 1, Generic Mechanical Design C r i t e r i a f o r BWR Fue l Designs, Advanced Nuclear Fuels Corporation, May 1995 ITS 3.2.31.

3.3.5 Deleted 3.3.6 XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology f o r B o i l i n g Water Reactors - Ne u tro n ic Methods f o r Design and Anal y s i s , Exxon Nuclear Company, March 1983 JTS 3.2.1, TS 3.2.2, TS 3.2.31, 3.3.7 XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology f o r B o i l i n g Water Reactors: A p p l i c a t i o n o f t h e ENC Methodology t o BWR Reloads, Exxon Nuclear Company, June 1986 [TS 3.2.1, TS 3.2.2, TS 3.2.31.

3.3.8 EMF-2158(P)(A) Revis io n 0, Siemens Power C o rp o ra tio n Methodology f o r B o i l i n g Water Reactors: E v a lu a tio n and V a l i d a t i o n o f CASW-MICROBURN-82, Siemens Power Corporation, October 1999 [TS 3.2.2, TS 3.2.31 .

3.3.9 XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology f o r B o i l i n g Water Reactors, THERMEX: Thermal L i m i t s Methodology Summary D e s c r i p t i o n , Exxon Nuclear Company, January 1987 [TS 3.2.21.

3.3.10 XN-NF-84-105(P)(A), Volume 1 and Supplements 1 and 2, XCOBRA-T: A Computer Code f o r BWR T r a n s ie n t Thermal H y d r a u l i c Core Analysis, Exxon Nuclear Company, February 1987 [TS 3.2.21.

3.3.11 ANF-524(P)(A) Rev i sio n 2 and Supplements 1 and 2, ANF C r i t i c a l Power Methodology f o r B o i l i n g Water Reactors, Advanced Nuclear Fuels Corporation, November 1990 [TS 3.2.21.

3.3.12 ANF-913 (P)(A), Volume 1, Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program f o r B o i l i n g Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990 [TS 3.2.21.

3.3.13 XN-NF-825(P)(A) Supplement 2, BWR/6 Generic Rod Withdrawal E r r o r Analysis, MCPRp f o r P l a n t Operation W i t h i n t h e Extended Operating Domain, Exxon Nuclear Company, October 1986 [TS 3.2.21.

3.3.14 ANF-l358(P) (A) Rev i s io n 3, The Loss o f Feedwater Heating Transient i n B o i l i n g Water Reactors, Framatome ANP, September 2005 [TS 3.2.21.

COLR Page 5 LDC 07011

CORE OPERATING LIMITS REPORT 3.3 Methodology References (continued) 3.3.15* EMF-l997(P)(A) Revision 0, "ANFB-10 C r i t i c a l Power C o r r e l a t i o n , ' ' Siemens Power Corporation, J u l y 1998 [TS 3.2.21.

3.3.16" EMF-l997(P), Supplement l ( P ) ( A ) , R e v i s i o n 0, "ANFB-10 C r i t i c a l Power C o r r e l a t i o n : High Local Peaking Results, Siemens Power Corporation," J u l y 1998 I T S 3.2.21.

3.3.17 EMF-2209(P)(A) Revision 2, "SPCB C r i t i c a l Power C o r r e l a t i o n , Siemens Power Corporation," September 2003 [TS 3.2.21.

3.3.18* EMF-2245(P)(A) Revision 0, " A p p l i c a t i o n o f Siemens Power C o r p o r a t i o n ' s C r i t i c a l Power C o r r e l a t i o n s t o Co-Resident Fuel," Siemens Power Corporation, August 2000 [TS 3.2.21.

3.3.19 EMF-2361 (P)(A) Revision 0, "EXEM BWR-2000 ECCS E v a l u a t i o n Model,"

Framatome ANP Richland, I n c . , May 2001 [TS 3.2.11.

3.3.20 Deleted 3.3.21 Deleted 3.3.22 Deleted 3.3.23 EMF-2292(P)(A) Revision 0, "ATRIUM-10: Appendix K Spray Heat Transfer C o e f f i c i e n t s , Siemens Power Corporation," September 2000 [TS 3.2.11.

3.3.24 EMF-CC-O74(P)(A) Volume 4 Revision 0, "BWR S t a b i l i t y Analysis-Assessment o f STAIF w i t h I n p u t from MICROBURN-B2," Siemens Power Corporation, August 2000 [TS 3.2.41.

3.3.25* MEDE-24011-P-AJ General E l e c t r i c Standard A p p l i c a t i o n f o r Reactor F u e l (GESTAR-11) [TS 3.2.1, TS 3.2.2, TS 3.2.31.

  • Note: These references are a p p l i c a b l e when GE f u e l i s i n the reactor. I COLR Page 6 LDC 07011

CORE OPERATING LIMITS REPORT 4.0 DEFINITIONS 4.1 Averaqe Planar Linear Heat Generation R a t e fAPLHGR) - the APLHGR s h a l l be a p p l i c a b l e t o a s p e c i f i c p l a n a r h e i g h t and i s equal t o t h e sum o f the l i n e a r heat generation r a t e s f o r a l l the f u e l rods i n the s p e c i f i e d bundle a t the s p e c i f i e d height d i v i d e d by t h e number o f f u e l rods i n the f u e l bundle.

4.2 Averaae Pl a n a r ExDOSUr? - t h e Average Planar Exposure s h a l l be a p p l i c a b l e t o a s p e c i f i c planar h e i g h t and i s equal t o t h e sum o f t h e exposure o f a l l t h e f u e l rods i n the s p e c i f i e d bundle a t the s p e c i f i e d h e i g h t d i v i d e d by t h e number o f f u e l rods i n t h e f u e l bundle.

4.3 C r i t i c a l Power Ratio fCPRL - t h e r a t i o o f t h a t power i n t h e assembly, which i s c a l c u l a t e d by a p p l i c a t i o n o f t h e f u e l vendors appropriate b o i l i n g c o r r e l a t i o n , t o cause some p o i n t i n the assembly t o experience b o i l i n g t r a n s i t i o n , d i v i d e d by t h e a c t u a l assembly operating power.

4.4 Core ODe r a t i n a L i m i t s ReDort fCOLRL - The Grand G u l f Nuclear S t a t i o n s p e c i f i c document t h a t provides core operating l i m i t s f o r t h e c u r r e n t reload c y c l e i n accordance w i t h Technical S p e c i f i c a t i o n 5 . 6 . 5 .

4.5 Linear Hea t Generation Rate f LHGR) - t h e LHGR s h a l l be t h e heat generation per u n i t l e n g t h of f u e l rod. I t i s the i n t e g r a l of t h e heat f l u x over t h e heat t r a n s f e r area associated w i t h t h e u n i t length.

4.6 Minimum C r i t i c a l Power R a t i o fMCPRL - the MCPR s h a l l be t h e smallest CPR which e x i s t s i n t h e core.

4.7 MCPR Safetv L i m i t - t h e minimum value o f t h e CPR a t which t h e f u e l could be operated w i t h the expected number o f rods i n b o i l i n g t r a n s i t i o n n o t exceeding 0.1% o f t h e f u e l rods i n t h e core.

4.8 Alianed D r i v e F l o y - Adjusted FCTR card i n p u t d r i v e f l o w s i g n a l t h a t accounts f o r a c t u a l v a r i a t i o n s i n t h e core f l o w t o d r i v e f l o w r e l a t i o n s h i p .

4.9 Monitored Reaion - The area o f the core power and f l o w operating domain where t h e r e a c t o r may be susceptible t o r e a c t o r i n s t a b i l i t i e s under c o n d i t i o n s exceeding t h e l i c e n s i n g b a s i s o f the c u r r e n t r e a c t o r system.

4.10 Pest r i c t e d Reaion - The area o f t h e core power and f l o w operating domain where t h e r e a c t o r i s susceptible t o r e a c t o r i n s t a b i l i t i e s i n the absence of r e s t r i c t i o n s on core v o i d d i s t r i b u t i o n s .

4.11 SetDoint Setuo - A FCTR card feature t h a t sets t h e normal non-setup E1A APRM flow-biased scram and c o n t r o l rod block t r i p reference s e t p o i n t s associated w i t h the Exclusion and R e s t r i c t e d Regions higher t o permit required r e a c t o r maneuvering i n t h e R e s t r i c t e d Region when s t a b i l i t y c o n t r o l s are i n e f f e c t .

4.12 Middle o f Cvcle fMOCI - The Cycle 16 MOC Core Average Exposure (CAE) i s 32,106 MWd/MTU [ 3 . 2 . 1 ] .

4.13 End o f Cvcle fEOC) - The Cycle 16 EOC CAE i s 34,063 MWd/MTU r3.2.11.

4.14 Extended End o f Cvcle fEEOC) - The Cycle 16 EEOC CAE i s 34,885 Wd/MTU

[3.2.1].

COLR Page 7 LDC 07011

CORE OPERATING L I M I T S REPORT 5.0 GENERAL REQUIREMENTS 5.1 Average Planar Linear Heat Generation Rates Consistent w i t h Technical S p e c i f i c a t i o n 3.2.1, a l l APLHGRs s h a l l n o t exceed t h e exposure-dependent l i m i t s reported i n Figure 1 - 1 [ 3 . 2 . 1 ] . I 5.2 Minimum C r i t i c a l Power R a t i o Consistent w i t h Technical S p e c i f i c a t i o n 3 . 2 . 2 , the MCPR s h a l l be equal t o o r g r e a t e r than t h e l i m i t s reported i n F i g u r e ( s ) 2 as f u n c t i o n s o f power, f l o w , and exposure [ 3 . 2 . 1 ] . I A d d i t i o n a l MCPR operating l i m i t s are provided t o support operation w i t h EOC-RPT inoperable as described i n Technical S p e c i f i c a t i o n 3 . 3 . 4 . 1 .

5.3 L i n e a r Heat Generation Rate Consistent w i t h Technical S p e c i f i c a t i o n 3 . 2 . 3 , the LHGR s h a l l n o t exceed t h e exposure-dependent l i m i t s reported i n Figure 3-1 m u l t i p l i e d by t h e smaller o f e i t h e r the power-dependent o r flow-dependent LHGR f a c t o r s reported i n Figures 3 - 2 and 3 - 3 , r e s p e c t i v e l y [ 3 . 2 . 1 ] . I The LHGR l i m i t s given i n Figure 3-1 may be l i n e a r l y extrapolated beyond a p e l l e t exposure o f 70.4 GWd/MTU provided t h e rod and f u e l assembly exposure l i m i t s are maintained [ 3 . 2 . 1 ] .

5.4 Stability The s t a b i l i t y regions and allowable values s p e c i f i e d i n Technical S p e c i f i c a t i o n s are reported i n Figure(s) 4 [ 3 . 2 . 2 ] .

5.5 Applicability The f o l l o w i n g core operating l i m i t s are applicable f o r operation i n t h e Maximum Extended Operating Domain (MEOD), w i t h Feedwater Heaters Out o f Service (FHOOS),

and EOC-RPT inoperable. For operation w i t h EOC-RPT inoperable, t h e a l t e r n a t e MCPR l i m i t s described i n Section 5 . 2 above must be implemented. Since t h e maximum l i c e n s e d GGNS feedwater temperature reduction i s 50 OF a t r a t e d power operation, an a l t e r n a t e s e t o f s t a b i l i t y l i m i t s i s not required. For s i n g l e - l o o p operation (SLO), the f o l l o w i n g a d d i t i o n a l requirements must be s a t i s f i e d .

1. A SLO WPLHGR m u l t i p l i e r o f 0.97 i s required [ 3 . 2 . 1 ] .

I

2. The MCPR s h a l l be equal t o o r greater than t h e l i m i t s determined i n accordance w i t h Section 5 . 2 above increased by 0.02 t o account f o r t h e d i f f e r e n c e between the two-loop and s i n g l e - l o o p MCPR s a f e t y l i m i t s f o r the allowable range o f s i n g l e - l o o p operation [ 3 . 2 . 1 ] .

COLR Page 8 LDC 07011

CORE OPERATING LIMITS REPORT l3T 0. 12.5 15,12.5 12 g 11 B

g 10 3

3 9 8

7 0 10 20 30 40 50 60 70 Average Planar Exposure ( G W M T U )

Figure 1-1 Maximum Average Planar Linear Heat Generation Rate Note: Actual limits described in Sectkns 5.1 end 5.5 COLR Page 9 LDC 0701 1

CORE OPERATING LIMITS REPORT 25, 1.82 1.88 - 1 > 50% Core flow 40,1.77 40,1.63

< 50% Core flow fE 1.5 I 1.4 1.2 1*3 1.1 t{ loo, 1.21 l.O! " " I " " I ' ' ' I " " I " " I " " I " ' ' I " " ; " " ; ' " ' +

0 10 20 30 40 50 60 70 80 90 100 Core Power (% Reted)

Figure 2-1 Cycle 16 Power-Dependent MCPR Limits BOC to MOC 2.0 -

1.9 -- 25, 1.88 > 50% Core flow 1.8 -- 25, 1.82 1.7 --

1.6 --

v -< 50% Core flow fE 1.5 --

0 40,1.51 Z 1.4 --

1.3 --

1.2 --

loo, 1.22 1.1 --

1.0 ' ' I Z I " ' / I " " : " " I " " : " " I " " : " " I " " : " " +

COLR Page 10 LDC 07011

CORE OPERATING L I M I T S REPORT 2.0 25,1.88 1.9 1.8 25, 1.82 1.6

-< 50% Core flow 0 70.1.42 I 1.4 L

1.3 --

70,1.31 1.2 -- lM),1.24 1.1 --

Figure 2-3 Cycle 16 Power-Dependent MCPR Limlts MOC to EOC 1.5 1.4 1.3 -- 70,1.31 *,\

1.2 -- loo, 1.26 1.1 --

1.0 " " 1 " " 1 " " ~ " " ~ " " ~ " ' 1 ~""~""~""~""'

COLR Page 11 LDC 07011

CORE OPERATING LIMITS REPORT

25. 1.88 25, 1.82 40.7.77 1.7 --

40,1.63 1.6 --

Y - 50% Core flow C

g 1.5 --

40,1.51 0

3i 1.4 --

1.3 --

1.2 -- 100. 1.24 1.1 --

1.0 ' " ' I " " I " " I " " ~ " " I " " ~ " " I " " I " ~ ' I " " 1 Figure 2-5 Cycle 16 Power-Dependent MCPR Limits EOC to EEOC 2.0 -

25, 1.88 1.9 --

1.8 -- 25, 1.82 1.7 --

- 1.6 --

1.5 --

-c 50% Core flow 0 40,1.51 70, 1.42 35 1.4 --

1.3 -- 70,l.S m 1.2 -- 100,1.27 1.1 --

1.0 t ' ' ' ' I ' ' ' ' I ' ' I ' I ' ' ' ' I ' ' ' ' : I ' ' ' I ' ' ' ' I ' ' ' ' I ' ' ' ' I ' ' ' ' I Figure 2-6 Cycle 16 Power-Dependent MCPR Limits EOC to EEOC with EOC-RPT Inoperable COLR Page 12 LDC 0701 1

CORE OPERATING L I M I T S REPORT 1.35 -

1.3 --

s 1.25 -I 0

I 1.2 --

I 1.15- ' I ' I I ' I ' ' I ' I ' I ' I ' I ' 1 Figure 2-7 Cycle 16 Flow-Dependent MCPR Limits COLR Page 13 LDC 07011

CORE OPERATING L I M I T S REPORT 0.95 --

2s 0

2 0.90-1 P

-I 0.85 --

0.80 -- 25.0.79 0.75 4 I a I I I a ' I I I I I I A I I I I I I I I I I I I I I I I I I ' I I I I a I I I a I 4 I I I I I ; 4 I I ' 1 1.05 8 8 20,1.0 105.1.0 0.95 s

2 0.85 P

-I 0.75 0.65 0 10 20 30 40 50 60 70 80 90 loo 110 Core Flow (%rated)

Figure 3-3 Cycle 16 Flow-Dependent LHGR Factor for ATRIUM-I0 Note: These factors to be applied to the exposure-dependent limits as described In Section 5.3 COLR Page 15 LDC 0701 1

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