ML20154C282

Responds to Re Submittal of Snoc Application for 8% Power Level Increase.Expresses Appreciation for Opportunity to Have Met with ACRS Subcommittee 980827 & 0902

ML20154C282
Person / Time
Site:	Hatch
Issue date:	09/29/1998
From:	Callan L NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:	Seale R Advisory Committee on Reactor Safeguards
References
NUDOCS 9810060217
Download: ML20154C282 (7)

Text

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• 5eptember 29, 1998 ff / 'fM Dr. R. L. Seale, Chairman Advisory Committee on Reactor Safeguards U. S. Nuclear Regulatory Commission <

Washington, DC 20555 l

SUBJECT:

STAFF RESPONSE TO ACRS LETTER OF SEPTEMBER 15,1998, ON EDWIN 1.

HATCH NUCLEAR PLANT, UNITS 1 AND 2, APPLICATION FOR EXTENDED POWER LEVEL INCREASE

Dear Dr. Seale:

l This is in response to your letter of September 15,1998, in which the Advisory Committee on

[ Reactor Safeguards (ACRS) endorsed the NRC staff's recommendation that the application i

submitted by Southern Nuclear Operating Company, Inc. (SNC) for an 8 percent power level t increase for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, be approved. The staff appreciates the opportunity to have met with the ACRS Subcommittee on Thermal-Hydraulic Phenomena on August 27,1998, and with the ACRS on September 2,1998, to discuss SNC's application. If you have any further questions related to this matter, please contact Leonard N.

Olshan (LNO), Project Manager for the Hatch plant, at 415-1419.

Sincerely,

'.J p a an Exe t' e Director for Operations cc: Chairman Jackson '

Commissioner Diaz .

i Commissioner McGaffigan l SECY

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September 29, 1998 Dr. R. L. Sente, Chairman Advisory Committee on Reactor Safeguards U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

STAFF RESPONSE TO ACRS LETTER OF SEPTEMBER 15,1998, ON EDWIN 1.

HATCH NUCLEAR PLANT, UNITS 1 AND 2, APPLICATION FOR EXTENDED POWER LEVEL INCREASE

Dear Dr. Seale:

This is in response to your letter of September 15,1998, in which the Advisory Committee on Reactor Safeguards (ACRS) endorsed the NRC staff's recommendation that the application submitted by Southern Nuclear Operating Company, Inc. (SNC) for an 8 percent power level increase for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, be approved. The staff appreciates the opportunity to have met with the ACRS Subcommittee on Thermal-Hydraulic Phenomena on August 27,1998, and with the ACRS on September 2,1998, to discuss SNC's application. If you have any further questions re!ated to this matter, please contact Leonard N.

Olshan (LNO), Project Manager for the Hatch plant, at 415-1419.

Sincerely, Origfmisignedby L. J. Callan L. Joseph Callan Executive Director for Operations Docket Nos. 50-321 and 50-366 cc: Chairman Jackson Commissioner Diaz Commissioner McGaffigan SECY Distribution:

See next page To receive a copy of this document, indicate in the box: "C" = Copy "N" = No copy l OFFICE PM:PDil-2* lE LA:PDil-2* l D:PDil-2" TECH ED l (A)D:DRPE* l NAME LOlshan:en LBerry HBerkow JZwolinski DATE 9/22/98 9/22/98 9/23/98 / /98 9/23/98 OFFICE ADPR:NRR* l D:NRR EDOo NAME BBoger SCollins LCa6fn_

DATE 9/23/98 / /98 7 /1f /98 / /

DOCUMENT NAME: G:\ HATCH \ACRS.RE8 OFFICIAL RECORD COPY Distribution for Green Ticket #G980567 cated

Distribution for Green Ticket #G980567 dated tantamhar 90. loon Docket File (w/originalincoming)

PUBLIC (w/ incoming)

EDO #G980567

- EDO Rdg.

LCallan HThompson .

AThadani, RES PNorry JBlaha .

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BSheron JRoe RZimmerman PD ll-2 Rdg. (w/ incoming)

JZwolinski HBerkow RLaskin, DRPE OGC

. OPA OCM SECY # CRC-98-0861 NRR Mailroom (EDO #G9890567 w/ incoming) (0-5-E-7)

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Dr. R. L. Seale, Chairman Advisory Committee on Reactor Safeguards U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

STAFF RESPONSE TO ACRS LETTER OF SEPTEMBER 15,1998, ON EDWIN 1.

HATCH NUCLEAR PLANT, UNITS 1 AND 2, APPLICATION FOR EXTENDED /

POWER LEVEL INCREASE f'

Dear Dr. Seale:

This is in response to your letter of September 15,1998, mittee on in whic Reactor Safeguards (ACRS) endorsed the NRC staff's recommendation that t plication '

submitted by Southern Nuclear Operating Company, rcent power Inc.

level (SNC) fo increase for the Edwin 1. Hatch Nuclear Plant, Units 1 and 2, be approved. The staff appreciates the opportunity to have met with the ACRS Subco ittee on Thermal-Hydraulic Phenomena on August 27,1998, and with the ACRS on S ptember 2,1998, to discuss SNC's application. If you have any further questions related o this matter, please contact Leonard N.

Olshan (LNO), Project Manager for the Hatch pla , of my staff at 415-1419.

S' cerely, l

l L. Joseph Callan  !

Executive Director I for Operations Docket Nos. 50-321 and 50-366 cc: Chairman Jackson i Commissioner Diaz Commissioner McGaffig SECY Djstribution:

See next page

- To receive a copy of this document, indicate in the box: "C" = Copy "N" = No copy TECH b / l OFFICE PM:PDll-2* lE LA:PDll-2* l D:PDil-2* l (A)D:DRPE* l NAME LOlshan:en LBerryn HBerkow X JZwolinski )

DATE 9/22/98 9/2#98 ) 9/23/98 // 19 8  % 9/23/98 OFFICE ADPR:NRR* , 9'NR7 U [- EDO  !

c 15W NAME BBoger LCallan i DATE 9/23/98 d/25/98 / 19 8 / /

DOCUMENT NAME: G:\ HATCH \ACRS.RES OFFICIAL RECORD COPY

Dr. R. L. Seale, Chairman Advisory Committee on Reactor Sakguards U. S. Nuclear Regulatory Commissi Washington, DC 20555

Dear Dr. Seale:

l This is in response to your letter of S9ptember 15,1998, in which the Advisory Committee on Reactor Safeguards (ACRS) endorsed th NRC staff's recommendation that the application submitted by Southern Nuclear Operating ompany, Inc. (SNC) for an 8 percant power level increase for the Edwin I. Hatch Nuclear Plan Units 1 and 2, be approved. The staff I

appreciates the opportunity to have met with t ACRS Subcommittee on Thermal-Hydraulic Phenomena on August 27,1998, and with the A RS on September 2,1998, to discuss SNC's application. If you have any further questions rela ed to this matter, please contact Leonard N.

Olshan (LNO), Project Manager for the Hatch plant, of my staff at 415-1419.

Sincerel ,

L. Joseph allan Executive irector for Opera ons Docket Nos. 50-321 and 50-366 cc: Chairman Jackson Commissioner Diaz Commissioner McGaffigan SECY Distribution:

See next page To receive a copy of this document, indicate in the box: "C" = Co r "N" = No copy OFFICE / PM:PDil-2 lE LA:PDil-2 ) I/l, D:P M h l TECH ED l (A)D:DJPEI l NAMEW LOlshan:cn LBerry_ $ / M 8erkc N V \ JZwoiie(M DATE 3 /ZZ/98 9 /7///98 'l/ D/98 \ / /98 7 /d /98 OFFICE ADPR:NRR()* l N b:NRR EDO l\ l NAME BBoger ()

hSCollins LCallan \

DATE (d I'l// ' / /98 / /98 ) / /

DOCUMENT NAME: G:\ HATCH \ACRS.RES OFFICIAL RECORD COPY

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EDO Principal Correspondence Control i

I FROMs DUE: 10/16/98

~~ EDO CONTROL: G980567 DOC DT: 09/15/98 FINAL REPLY:-

R. L._ Seale', ACRS

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Callan, EDO FOR SIGNATURE OF : ** GRN **

CRC NO: 98-0861

-Callan, EDO DESC ROUTING:

APPLICATION FOR' POWER. LEVEL INCREASE FOR EDWIN I. Callan

, HATCH NUCLEAR' POWER PLANT UNITS 1 AND 2 -Travers Thompson-Norry Blaha Burns

- DATE: 09/17/98 Thadani, RES Paperiello,NMSS ASSIGNED TO: CONTACT: Martin,_AEOD Mitchell, OEDO

_NRR Collins ACRS File iSPECIAL INSTRUCTIONS OR REMARKS:

- Pr: pare response to ACRS for EDO signature. Add Commissioners and SECY as cc's.

USE SUBJECT LINE IN RESPONSE.

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PAPER-NUMBER: -CRC 298-0861-- LOGGING DATE: Sep 16 98 I

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i AUTHOR:~ 'R.L.SEALE:

.  ; AFFILIATION: l ADVISORY' COMMITTEE ON' REACTOR SAFEGUARDS- ')

e i (ADDRESSEE: JL' JOSEPH.. CALLAN, EDO.

LETTER DATE:- iSep;15.l98 FILE ' CODE : : OM-7. ACRS y.-

SUBJECT:

~ APPL FOR-POWER: LEVEL INCREASE FOR EDWIN I HATCH

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NUCLEAR: POWER PLANT 1 UNITS 1 AND 2

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g ADVISORY COMMITTEE ON REACTOR SAFEGUARDS g WASHINGTON, D. C. 20555 ~

..... u September 15,1998  !

I Mr. L. Joseph Callan i i' Executive Director for Operations i U.S. Nuclear Regulatory Commission l Washington DC 20555-0001 l i

Dear Mr. Callan:

l

SUBJECT:

- APPLICATION FOR POWER LEVEL INCREASE FOR EDWIN 1. HATCH NUCLEAR POWER PLANT UNITS I AND 2 During the 455th meeting of the Advisory Committee on Reactor Safeguards, September 2-4, 1998, we reviewed the application by the Southern Nuclear Operating Company, Inc. (SNC) for

..a power levelincrease for the Edwin I. Hatch Nuclear Power Plant Units 1 and 2. Our Subcommittee on Thermal-Hydraulic Phenomena discussed this matter on August 27,1998.

During these meetings, we had the benefit of discussions with representatives of General Electric Nuclear Energy (GENE), SNC, and the NRC staff. We also had the benefit of the

' documents referenced.

The SNC has requested an eight percent power level increase for each unit of the Hatch plant to permit power operation up to 2763 MWt. The current rated power for each unit is 2558 MWt (a five percent power level increase had been approved earlier under the original GENE generic

< power uprate program). The current request for an additional eight percent power level ,

increase utilized the GENE generic guidelines [ Licensing Topical Report (LTR) NEDC-32424P]

O and generic evaluations [LTR NEDC-32523P] developed for the " Extended Power Uprate" program. This generic program is intended to ensure that the extended power uprate application will either meet a!! the regulatory requirements or have only justifiable exceptions.

.f in its application, the SNC took minor exception in the area of startup test recommendations. In

~ our July 24,1998 report, we concurred with the GENE generic guidelines and evaluations as "qua,lified by the staff's safety evaluation reports.

.The power increase for the Hatch units is accomplished by flattening the radial power profile while holding the peak bundle power constant. The core exit steam quality is increased.-

E. ' Additional steam flow requires small increases in feedwater flow and reactor recirculation pump speed. The additional flow is well within the capacity of the separator and dryer system.

Significant increase in the reactor vessel pressure is avoided by modifying the high-pressure L- i- stage of the steam turbines. The reactor core pwer/ flow map is expanded along the current l ' load line limit" so that the maximum core flow limit does not exceed the pre-uprate value. A L ' detect-and-suppress system is used by SNC to deal with boiling water reactor instability L

EDO -- G980567

l 1

2 concerns. This system utilizes closely spaced individual local power range monitor neutron flux  ;

detectors, combined into cells, to detect any local or global instability (Option 111 of Supplement 1 to NRC Bulletin 88-07 and NRC Generic Letter 94-02). Other changes include modification of some balance-of-plant systems; recalibration of plant instrumentation, including changes in set points; and appropriate modification of plant procedures.

The NRC provides criteria in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists in any proposed license amendment. On the basis of its evaluation, the staff concluded that the requested power level increase does not involve a significant hazards consideration. The staff found the analyses, methods, and results submitted by SNC to be acceptable.

The SNC presented substantial probabilistic risk analyses and uncertainty evaluations to support a risk-informed decision process. These analyses included reviews of initiating event frequencies, equipment failure rates, operator errors, and success criteria. Qualitative arguments were used to establish that the contributions of fire, external events, and events under shutdown conditions to CDF are likely to be acceptably small. The effects of power uprate on the expected value of the large, early-release frequency were shown to be small.

The results of the analyses showed that the most risk-significant effect of the power uprate was a change in the failure probability associated with the operator action to depressurize when inadequa'.e high-pressure injection exists. The resulting change in core damage frequencies (ACDF) for Units 1 and 2 is less than 104 per year at a base CDF (for internal events) of about 2 X 104 per year.

We concur with the conclusions of the staff that the requested license amendment meets all regulatory requirements for adequate protection and does not pose undue risk to the health and safety of the public. Therefore, we agree with the staff's recommendation for approval of the requested eight percent power level increase for tne Edwin 1. Hatch Nuclear Plant Units 1 and 2.

Sincerely, R. L. Seale Chairman Referencer

1. Memorandum dated August 14,1998, from H. N. Berkow, Office of Nuclear Reactor Regulation, to J. T. Larkins, ACRS, transmitting draft Safety Evaluation Supporting Southern Nuclear Operating Company, Inc., Application for Edwin I. Hatch Power Uprate.

2. Letter dated August 8,1997, from H. L. Sumner, Jr., Southern Nuclear Operating Company, Inc., to U.S. Nuclear Regulatory Commission, transmitting Edwin 1. Hatch Nuclear Plant Request for License Amendment, Extended Power Uprate Operation (contains proprietary information).

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( 3. Letter dated March 9,1998, from H. L. Sumner, Jr., Southem Nuclear Operating l Company, Inc., to U.S. Nuclear Regulatory Commission, transmitting Response to l Request for Additional information on Extended Power Uprate License Amendment L Request.

l 4. Letter dated May 6,1998, from H. L. Sumner, Jr., Southern Nuclear Oparating

! Company, Inc., to U.S. Nuclear Regulatory Commission, transmitting Response to l Request for Additional Information on Extended Power Uprate License Amendment

Request.  !

! 5. Letter dated July 6,1998, from H. L. Sumner, Jr., Southern Nuclear Operating  !

Company, Inc., to U.S. Nuclear Regulatory Commission, transmitting Response to Request for Additional Information on Extended Power Uprate License Amendment l Request (contains proprietary information). l

( 6. Letter dated July 24,1998, from R. L. Seale, Chairman, ACRS, to L. Joseph Callan, l Executive Director for Operations, NRC,

Subject:

General Electric Nuclear Energy Extended Power Uprate Program and Monticello Nuclear Generating Plant Power Level increase Request.

7. Letter dated July 31,1998, from H. L. Sumner, Jr., Southern Nuclear Operating Company, Inc., to U.S. Nuclear Regulatory Commission, transmitting Response to Request for Additional Information on Extended Power Uprate License Amendment.

8. Letter dated April 17,1997, from H. L. Sumner Jr., Southern Nuclear Operating Company, Inc., to U.S. Nuclear Regulatory Commission, transmitting Revised Post-LOCA Doses.

9. Letter dated March 22,1996, from W. Marquino, GE Nuclear Energy, to U.S. Nuclear Regulatory Commission, transmitting Generic Evaluations of General Electric Boiling Water Reactor Extended Power Uprate, NEDC-32523P, March 1996, and NEDC-32523P Supplement 1, Volumes I & II, June 1996 (Proprietary).

10. GE Nuclear Energy Report NEDC-32424P, " Generic Guidelines for General Electric ,

Boiling Water Reactor Extended Power Uprate," February 1995 (Proprietary).

11. Letter dated February 8,1996, from D. Crutchfield, NRC, to G. Sozzi, General Electric Nuclear Energy, transmitting Staff Position Concerning General Electric Boiling Water Reactor Extended Power Uprate Program.

12. Memorandum dated May 18,1998, from E. G. Adensam, Office of Nuclear Reactor Regulation, to John T. Larkins, ACRS, transmitting Staff Position Concerning GE Licensing Topical Report, NEDC-32523P on Generic Evaluation of Boiling Water l Reactor Extended Power Uprate.

13. U. S. Nuclear Regulatory Commission Bulletin 88-07, Supplement 1: Power Oscillations in Boiling Water Reactors (BWRs), dated December 30,1988.

14. U.S. Nuclear Regulatory Commission Generic Letter 94-02: Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors, dated July 11,1994.

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