ML20066D920

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Forwards Nonproprietary Rev 2 to ANF-90-022, Grand Gulf Unit 1,Cycle 5 Reload Analsis, Proprietary Rev 2 to ANF-90-021, Grand Gulf Unit 1,Cycle 5 Plant Transient Analysis & Vols 1 & 2 to ANF-89-171(P)
ML20066D920
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 01/09/1991
From: Cottle W
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19310E502 List:
References
GNRO-91-00003, GNRO-91-3, NUDOCS 9101170128
Download: ML20066D920 (19)


Text

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January 9, 1991 w. T. cottie

. 4 m U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 Ati.ention: Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station Unit 1  !

Docket No. 50-416 License No. NPF-29 >

Current Cycle Safety Analysis, Revision 3 GNRO-91/00003 Gentlemen:

Entergy Operations, Inc. hereby transmits one signed original and ten copies of Revision 3 to the Current Cycle Safety Analysis (CCSA), for L Grand Gulf Nuclear Station (GGNS).

The'CCSA provides information on the current GGNS fuel cycle operations and contains analyses supporting operation and the current fuel reload.

Analyses included in the CCSA have been approved by the NRC either through specific review of the GGNS reload applications or as topical reports submitted by vendors.

The CCSA was ce.veloped to provide a convenient source for current accident and tra.nsient analyses. The CCSA is considered part of the Updated Final Safety Analysis Report (UFSAR), and will be updated at least within 60 days of the start of every cycle. Revision 2 was submitted June 30, 1989 (AECM-89/0110) and reflected analyses to support =

GGNS Cycle 4. This revision to the CCSA reflects the Cycle 5 fuel reload accomplished during the fourth GGNS refueling outage which occurred in late 1990.

The Advanced Nuclear Fuels (ANF) Corporation report, ANF-89-171(P),

Volumes 1 and 2, submitted as part of Attachment 2 to this letter contains information considered by ANF to be proprietary. In accordance l with 10CFR2.790(b), the enclosed affidavit (Attachment 1) executed by R. A. Copeland of ANF provides the necessary information to support the withholding of the subject report from public disclosure.

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f January 9, 1991 GNRO-91/00003 Page 2 of 3 As required by 10CFF50.71(c)(2) and as authorized by Entergy Operations, I hereby certify, to the best of my knowledge, Information and belief, that the information given in the attached CCSA Revision 3 accurately represents changes made since the previous submittal, necessary to reflect information and analyses submitted to the NRC or prepared pursuant tn NRC requirement.

If you have any questions, please contact this o'fice.

Yours truly, 4m T" W WTC/ PRS /ams attachment: 1. ANF Affidavit

2. CCSA Revision 3 cc: Mr. D. C. Ilintz (w/c)

Mr. J. Mathis (w/a)

Mr. R. B. McGehne (w/o)

Mr. N. S. Reynolds (w/o)

Mr.11. L. Thomas (w/o)

Mr. Stewart D Ebnet.cr (w/a)

Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georg ia '0323 Mr. L. L. Kintner, Project Manager (w/o)

Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Hall Stop 11D21 Washington, D.C. 20555 A9012072/SNLICFLR - 2

f: 1 Attachment l'to GNRO-91/00003 i l

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ADVANCED NUCLEAR FUELS CORPORATION .

AFFIDAVIT [

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COUNTY 07 BENTON )

I, R. A. Copoland being duly sworn, hereby say and depose:

1. 1.am Manager, Reload Licensing, for Advanced Nuclear Fuols Corporation,

("ANF"), and as such I am authorized to oxocute this Affidavit.

2. I am familiar with ANF's detailed document control system and policies which

_ govern the protection and control of information.

5. I am famillar with the topical report ANF-89-171(P), Volumos 1 and 2 ontitled

" Grand Gint 1 ANF 1.4 Design Report Mechanical, Thermal-Hydraulic and Neutronic Design for Advanced Nuclear Fuels 9x9 5 Fuel Assemblies," referred to as " Document." information contained in this Document has boon classified by ANF as propriotary in accordance with the control system and policios established by ANF for the control and protection of information,

4. The Document contains information of a propriotary and confidential nature and is of tho type customarily hold in confidence by ANF and not made available to the public.

Based on my experience, I am aware that other. companies rogard information of the kind contained in the Document as proprietary and confidential.

5. The Document has beeri made available to the U.S. Nuclear Regulatory Commission in confidence, with the request that tho information contained in the Document will not be disclosed or divulgod, t ._ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ - _ _ _ _

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AFFIDAVIT Page 2

6. The Document contains information which is vital to a competitive advantage of ANF and would be helpful to competitors of ANF when competing with ANF.
7. The information contained in the Document is considered to be proprietary by ANF because it reveals certain distinguishing aspects of ANF licensing methodology which secure competitive advantage to ANF for fuel design optimization and marketability, and includes information utilized by ANF in its business which affords ANF an opportunity to obtain a competitive advantage ever its competitors who do not or may not know or use the information contained in the Document.
8. The disclosure of the proprietary information contained in the Document to a competitor would permit the competitor to reduce its expenditure of money and manpower and to improve its competitive position by giving it valuable insights into ANF licensing methodology and would result in substantial harm to the competitive position of ANF.
9. - The Document contains proprietary information which is held in confidence by ANF and is not available in public sources.
10. . In accordance with ANF's policies governing the protection and control of information, proprietary information contained in the Document has been made available, on a limited basis, to others outside ANF only as required and under suitable agreement providing for nondisclosure and limited use of the information.
11. ANF policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
12. -Information in this Document provides insight into ANF licensing methodology _

developed by ANF. ANF has invested significant resources in developing the methodology as

AFFIDAVIT Page 3 well as the strategy for this application. Assuming a competitor had available the same background data and incentives as ANF, the competitor n ::n, at a minimumi develop the information for the same expenditure of manpower and money as ANF.

THAT the statements made hereinabove are, to the best of my knowledge, information,

, and belief, truthful and complete.

FURTHER AFFIANT SAYETH NOT.

r SUBSCRIBED before me this /0 day of October .1990.

cM ON (u_

Susan K. McCoy N NOTARY PUBLIC, STATE OF A INGTON MY COMMISSION EXPIRES: 1/1 2

Attachment 2 to GNRO-91/00003 REVISION 3 0F Tile GGNS UNIT 1

> CURRENT CYCLE SAFETY At!ALYSIS A9012072/SNLICFLR - 5

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- CCSA n

L Entergy Operations, Inc.

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 Revision 3 Instructions For Filing Revision 3 1,- Insor't the " Revision 3" tab, transmittal le"cer (GNRO-91/00003) and this instruction sheet into the back of the CCSA Volumn.

2.. Remove and insert the pages and topical reports listed below. Dashes

(---) in the remove or insert column indicato no action required.

REMOVE INSERT CCSA Cover Sheet CCSA Cover Sheet TAB, "Page Index" Page Index Table of Contents- Table ,f Contents Introduction (all pages) Introduction (all pages)

ANF-88-1' (all pages) ANF-90-022, Revision 2 (all pages)

ANF-88-15.-(all pages) ANF-90-021, Revision 2 (all pages)

XN-NF-80-19(P)( A), Volume 4, ----

Revision 1.(all pages)

XN-NF-80-19(P), Volume 4, ----

Supplement ~1 (all pages)

NESDQ-88-003 Revision 0- ANF-89-171(P), Volumes 1 and'2 (all-pages) (all pages) t r

A9012072/SNalCFLR - 6 u

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GRAND GULF NUCLEAR STATION UNIT 1 CUP 2ENT CYCLE SAFETY ANALYSIS (CCSA) i M9012071/SNLICFLR - 1 Rev. 3 01/91 .3 1

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00 CCSA J' AGE INDEX Page Revision Cover Sheet 3 Page Index 3 Tabic of Contents 3 Introduction Cover 3 Sheet 1 3 2 a 3 3 4 3 5 3 6 3 3

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M9010152/SNLICFLR 1 Rev. 3 01/91

CURRENT CYCLE SAFETY ANALYSIS

-(CCSA)

Table of Contents Tab Description 1- Introduction 2 ANF-90-022 Grand Gulf Unit 1 Cycle 5 Reload Analysis Revision 2 3

3 ANF-90-021 Grand Gulf Unit 1 Cycle 5 Plant Transient Revision 2 Analysis 4 XN-NP-86-37 (P) Generic LOCA Break Spectrum Analysis for BWR/6 Plants 5 Deleted 6 XN-NF-825 (P)(A) BWR/6 Generic Rod Withdrawal Error Analysis, Supplement 2 MCPR for Plant Operations Within the Exte8ded Operating Domain 7 ANP-88-183 (P) Grand Gulf Unit i Reload XN-1.3, Cycle 4 3 Mechanical Design Report 8 ANF-89-171 (P) Grand Gulf 1 ANF-1.4 Design Report Mechanical, Volumes 1 and 2 Thormal-Hydraulic and Neutronic Design for Advanced Nuclear Fuels 9x9-5 Fuel Assemblies Revision 0 AECM-87/0234 Transmittal letter Revision 1 AECM-88/0188 Transmittal letter and Revision 1 Insert Instructions ,

Revision 2 AECM-89/0110 Transmittal letter and Revision 2 Insert Instructions Revision 3 GNRO-91/00003 Transmittal letter and Revision 3 Insert Instructions 3

M9010151/SNLICFLR 1 Rev. 3 01/91 3

INTRODUCTION 3

M9012071/SNLICFLR - 2 Rev. 3 01/91 3

l.0 Background Performing 10CFR50.59 evaluations requires the review of analyzed events presented in the UFSAR. In the process of performing such evaluations, it was  ?

recognized that the UFSAR annual revision may not include reload analyses performed for the current plant operating cycle due to the relative timing of the cycle startup and the revision submittal.

It was further recognized that some of the analyses presented in the UFSAR form the basis for subsequent analyses performed for future cycles.

These analyses typically require little revision from cycle to cycle unless a significant change in fuel type or methodology is made. The reload analyses 3

that are repeated each cycle address such changes in fuel type or methodology and either complement or are based on these " baseline" analyses provided in the UFSAR. Also, during any given cycle, additional analyses may be performed l 3 to support operations, procedural changes, technical specification changes, etc.

To provide a ready access to current cycle analyses and their relationship to baseline analyses for 10CFR50.59 and other evaluations, this

" Current Cycle Safety Analysis" (CCSA) document was developed. Analyses included in the CCSA have been approved by the NRC either through specific review of Entergy Operations applications or as topical reports submitted by l3 vendors. The CCSA is considered part of the UFSAR, is controlled by administrative procedure, and is maintained current consistent with 10CFR50.71(e).

The CCSA offers a convenient means apart from the UFSAR annual revjalon to provide the latest accident and transient analysis results to personnel using this information. It is intended that the CCSA will be updated at least within 60 days of the start of every cycle, and more frequently depending on the nature and scope of changes accumulated. l3 2.0 . Scope and Description The CCSA is related to the UFSAR as an integral updated document. 3 Sections in the UFSAR that are af fected by subsequent analyses presented in the CCSA-refer the reader to the CCSA and, therefore, the current analyses.

It is intended that before performing a review of analyses presented in -

the UFSAR, the reader is to consult Table 1 of the CCSA 9nd determine whether the analysis of interest is included in the CCSA. If the analysis is in the CCSA, the review should commence with the document in the CCSA assisted by baseline information presented .n the UFSAR,'as required. If the analysis is not in the CCSA,-it is an Indication that the information in the UFSAR represents the latest analyses on that subject and that the review should

. proceed using the UFSAR.

The UFSA; will be revised annually to include information from the CCSA that is judged to be of a permanent baseline nature. This information will 3

then be deleted from the CCSA. The UFSAR will also include references directing the reader to the appropriate sources for analysis not incorporated in the specific sections of-the UFSAR.

M9010152/SNLICFLR 1 Rev. 3 01/91 j$

The non-baselinn cycle related analyses that are presented in the CCSA 3 provide the current cycle analyses. These are replaced as they become superseded each cycle.

2.1 Analyzed Events The analyzed events presented in the CCSA are those for which the description contained in the UFSAR is not applicable to the current cycle.

Analyses described in the UFSAR that are still applicable to the plant in the current cycle are not presented in the CCSA. Thus, sections in the UFSAR that 3 do not refer to the CCSA are applicable as presented. For those sections that contain a reference to the CCSA, a review of the analyses presented in the CCSA is required.

2.2 Presentation of Analyzed Events CCSA analyses are provided as attachments identified by their document numbers. A listing of these documents along with titles and the events analyzed is provided in Section 3.0 below.

2.3 UFSAR-CCSA Cross Reference Listing Table 1 " Summary of Analyzed Events" provides a cross-reference listing of UFSAR events analyzed for the current cycle to CCSA attachments. Table 1 relates the event with its UFSAR section, the primary purpose for analyzing 3

.the event, and the CCSA attachmerit containing the current cycle analysis of this event.

For the sake of completeness, UFSAR sections presenting methodologies, design bases, and design descriptions have also been listed to provide an appropriate cross-reference to vendor information for these modeling issues.

The " event" column states " Methods" for these entries.

2.3.1 This section provides explanation of column headings found in Table 1.

UFSAR -

The Section in the UFSAR in which this event in Section addressed. If the event has not been previously addressed in the UFSAR, it is so stated, j3 Event -

This column identifies the event analyzed.

Primary -

The primary purpose (parameter and/or conditions Purpose evaluated) for performing this specific analysis.

CCSA -

Identifies the appropriate G:SA attachment which Attachment provides the analysis description and results for the event of interest.

M9010152/SNLICFLR 2 Rev. 3 01/91 3

L 12.3.2 The following defines acronyms used in Tablo 1, CPR -

Critical Power Ratio CS -

Coro Stability ELL -

Extended Lond Lino FLE -

Fuel Loading Error 1

FWCF -

foodwater Controllor Falluro '

FWil0S -

Foodwater ileator Out of Servico ICF -

Increased Corn Flow LOFWil -

Loss of Foodwater llonting transient l

LRND -

Load Reject No Bypass-(also known as GLR for Generator Load Rejection)

RDA -

Rod Drop Accident RWE -

Rod Withdrawal Error SLHCPR -

Safety Lim.lt MCPR SLO -

Single Loop Operation

-3.0 CCSA Attachments Tho- following lists attachments found in the CCSA.

1. -ANF-90-022 Grand Oulf Unit 1 Cycle 5'Roload Analysis Revision 2 Event - SI.0 ;

LOCA; CS; FLE; RDA.

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2. ANF-90-021 Grand Grand Unit 1 Cycle 5 Plant Transient Analysia Rovision 2 Even t. : LOFWil; FWCF; LRND; RWE; Flow Excursion; Overprossurization
3. XN-NF-86-37 (P) Generic LOCA Dreak Spectrum Analysis for BWR/6-Planta Event: LOCA
4. Deleted
5. XN-NF-825 (P)(A) BWR/6 Conoric Rod Withdrawal Error Analysis, Supplomont 2 HCPR for Plant. Operations Within the Extended 2h OperEtIng Domain M9010152/SNLICFLR 3 Rev. 3 01/91
6. ANF-88-183 (P) Grand Gulf Unit 1 Reload XN-1.3, Cycle 4 ,

Mechanical Design Report I

7. ANF-89-171 (P) Grand Gulf 1 ANF-1.4 Design Report Mechanical, Volumes 1 and 2 Thermal-Hyrdraulic and Neutronic Design for Advanced Nuclear Fuels 9x9-5 Fuel Assemblies l

M9010152/SNLICFLR 4 Rev. 3 01/91 3 l

TABLE 1 Summary of Analyzed Events UFSAR SECTION EVENT PRIMARY PURPOSE CCSA ATTACHMENT 4.1 Methods General analysis ANF-90-022 techniques, summary fuel description 4.2 Methods Fuel mechanical design ANF-90-022 description ANF-88-183 (P)

ANF-89-171'(P) 4.3- Methods Nuclear design ANF-90-022 description 4.4 Methods Thermal-hydraulic ANF-90-022  ;

design description 4.4'.4.6 CS Define detect and ANF-90-022 suppress region 5.2.2 Overpressurn Overpressure ANF-90-021 protection SA- ASME over- MSIV closure Max ANF-90-022 pressurization pressure ANF-90-021 3

6.3.3 ECCS Peak Clad ANF-90-022 Performance Temperature '

.15.0.3.3- Safety Limit SLMCPR ANF-90-022 ANF-90-021 15.1.1 LOFWH CPR with reduced FW' ANF-90-021 temperature 15.1.2- FWCF- CPR at rated ANF o^-021

-15D -FWCF CPR with ICF ANF .'0-021 15D- FWCF CPR with ELL ANF-90-021

-15D 15/CF CPR ac Power below ANF-90-021 40% (w/o direct scram) 15D FWCF CPR - w/o bypass ANF-90-021 ISD FWCF CPR with FWHOS ANF-90-021 M9010152/SNLICFLR 5 Rev. 3 01/91

1 I

l TABLE-1 Summary of Analyzed Events (Cont.)-

UFSAR SECTION EVENT PR1HARY PURPOSE CCSA ATTACllMENT l i

-15.2.2 LRNB CPR at rated ANF-90-021 1

15D LRNB CPR with ICF ANF-90-021 )

i 15D LRNB CPR with ELL ANF-90-021 15D LRNB CPR at power below ANF-90-021 40% (w/o direct scram)

ISC SLO Operation with one ANF-90-022 loop out of service 15.4.1, 2 RWE CPR vs. Power ANF-90-021 3 XN-NF-825 (P)(A),

Supplomont 2 15.4.7 FLE CPR - Misloaded ANF-90-022 bundle 15.4.9 RDA Enthalpy ANF-90-022 deposition 15.6.5 LOCA Dotormino break' XN-NF-86-37 (P) location, limiting-break size 15D Flow Runout- CPR & MAPLilGR- :ANP-90-021 vs. Flow t -.

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