ML073170088

Issuance of Amendments Regarding Control Rod Scram Time Testing Frequency (TAC MD5722 and MD5723)

ML073170088
Person / Time
Site:	Hatch
Issue date:	11/26/2007
From:	Martin R E NRC/NRR/ADRO/DORL/LPLII-1
To:	Madison D R Southern Nuclear Operating Co
Martin R E, NRR/DORL, 415-1493
Shared Package
ML073170098	List: ML073170088
References
TAC MD5722, TAC MD5723
Download: ML073170088 (12)

Text

November 26, 2007

Mr. Dennis R. Madison Vice President - Hatch Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING CONTROL ROD SCRAM TIME TESTING FREQUENCY, TSTF-460 (TAC NOS. MD5722 AND MD5723)

Dear Mr. Madison:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 254 to Renewed Facility Operating Li cense DPR-57 and Amendment No. 198 to Renewed Facility Operating License NPF-5 for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated June 5, 2007, as supplemented on June 11, 2007.

The amendments revise the TSs testing frequency for the surveillanc e requirement in TS 3.1.4, "Control Rod Scram Times," from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1."

A copy of the related Safety Ev aluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/ Robert E. Martin, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-321 and 50-366

Enclosures:

1. Amendment No. 254 to DPR-57

2. Amendment No. 198 to NPF-5

3. Safety Evaluation

cc w/encls: See next page

, Mr. Dennis R. Madison Vice President - Hatch Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING CONTROL ROD SCRAM TIME TESTING FREQUENCY, TSTF-460 (TAC NOS. MD5722 AND MD5723)

Dear Mr. Madison:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. to Renewed Facility Operating Li cense DPR-57 and Amendment No. to Renewed Facility Operating License NPF-5 for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated June 5, 2007, as supplemented on June 11, 2007.

The amendments revise the TSs testing frequency for the surveillanc e requirement in TS 3.1.4, "Control Rod Scram Times," from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1."

A copy of the related Safety Ev aluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, /RA/ Robert E. Martin, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-321 and 50-366

Enclosures:

1. Amendment No. 254 to DPR-57

2. Amendment No. 198 to NPF-5

3. Safety Evaluation

cc w/encls: See next page DISTRIBUTION: Public RidsAcrsAcnwMailCenter LPL2-1 R/F GHill (4 hard copies)

RidsNrrDorlLpl2-1 (EMarinos) RidsNrrDirsItsb (TKobetz)

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Package No. ML073170098 Amendment No. ML073170088 Tech Spec No. ML *SE transmitted by memo dated OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA DIRS/ITSB/BC NRR/LPL2-1/BC

NAME RMartin:nc MO=Brien TKobetz EMarinos DATE 11/15 /07 11 /13/07 10/12/2007*

11 /20/07 OFFICIAL RECORD COPY SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY

OGLETHORPE POWER CORPORATION

MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA

CITY OF DALTON, GEORGIA

DOCKET NO. 50-321

EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.1

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 254 Renewed License No. DPR-57

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Renewed Facility O perating License No. DPR-57 filed by Souther n Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated June 5, 2007, as supplemented June 11, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility O perating License No. DPR-57 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 254, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specificat ions and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance and shall be implemented within 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-57 and the Technical Specifications

Date of Issuance: November 26, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 254

RENEWED FACILITY OPERATING LICENSE NO. DPR-57

DOCKET NO. 50-321

Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages License License Page 4 Page 4

TSs TSs 3.1-10 3.1-10 B 3.1-22 B 3.1-22

SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY

OGLETHORPE POWER CORPORATION

MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA

CITY OF DALTON, GEORGIA

DOCKET NO. 50-366

EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE

Amendment No. 198 Renewed License No. NPF-5

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Renewed Facility O perating License No. NPF-5 filed by Souther n Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated June 5, 2007, as supplemented June 11, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility O perating License No. NPF-5 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 198, are hereby incorporated in the license. Southern

Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance and shall be implemented within 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facililty Operating License No. NPF-5 and the Technical Specifications

Date of Issuance: November 26, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 198

RENEWED FACILITY OPERATING LICENSE NO. NPF-5

DOCKET NO. 50-366

Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages License License Page 4 Page 4

TSs TSs 3.1-10 3.1-10 B 3.1-22 B 3.1-22

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 254 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 198 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2

DOCKET NOS. 50-321 AND 50-366

1.0 INTRODUCTION

By application dated June 5, 2007 (Agencywide Documents and Management System (ADAMS)

No. ML071560598), and supplemented June 11, 2007 (ADAMS No. ML071620283), Southern Nuclear Operating Company, Inc. (SNC, the licensee), requested changes to the Technical Specifications (TSs) for the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (Hatch 1 and 2).

The proposed changes would revise the TSs testing frequency for the surv eillance requirement (SR) in TS 3.1.4, "Control Rod Scram Times." Specifically, the proposed change would revise the frequency for SR 3.1.4.2, control rod scram time testing, from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1."

These changes are based on TS Task Force (TSTF) change traveler TSTF-460 (Revision 0) that has been approved generically for the boiling-water reactor (BWR) Standard TS, NUREG 1433 (BWR/4) and NUREG-1434 (BWR/6) by revising the frequency of SR 3.1.4.2, control rod scram time testing, from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1." A notice announcing the availability of this proposed TS change using the consolidated line item improvement process was published in the Federal Register on August 23, 2004 (69 FR 51864).

2.0 REGULATORY EVALUATION

The TS requirement gover ning the control rod scram time surveillanc e is intended to assure proper function of control rod insertion. Following each refueling outage, all control rod scram times are verified. In addition, periodically during power operation, a representative sample of control rods is selected to be inserted to verify the insertion speed. A representative sample is defined as a sample containing at least 10 percent of the total number of control rods. The current TS stipulates that no more than 20 percent of the control rods in this representative sample can be "slow" during the post-outage testing. With more than 20 percent of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 20-percent criterion (e.g., 20 percent of the entire sample size) is satisfied, or until the total number of "slow"

control rods (throughout the core, from all surveillances) exceeds the Limiting Condition for Operation limit. For planned testing, the control rods selected for the sample should be different for each test. This acceptance criterion for at-power surveillance testing will be redefined from 20 percent to 7.5 percent and will be incorporated into the TS Bases in accordance with its Bases Control Program. This ti ghtened acceptance criterion for at-power surveillance aligns with the TS 3.1.4 requirement for the total control rods allowed to have scram times exceeding the specified

limit.

The proposed change does not affect any current operability requirements and the test frequency being revised is not specified in regulations. As a result, no regulatory requirements or criteria are affected.

3.0 TECHNICAL EVALUATION

3.1 Statement

of Proposed Changes

Hatch 1 and 2 TS SR 3.1.4.2 states "verify, for a representative sample, each tested control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure >800 psig." SR 3.1.4.2 has a frequency of "120 days cumulative operation in MODE 1." The proposed change revises the frequency to "200 days cumulative operation in MODE 1." The TS Basis for SR 3.1.4.2 will be revised to reference the new frequency and to reduce the percentage of t he tested rods which can be "slow" from 20 percent to 7.5 percent.

3.2 Evaluation

of Proposed Change

The control rod insertion (scram) time test results at Hatch 1 and 2 have shown the control rod scram rates to be highly reliable. In its submittal dated June 5, 2007, and amended June 11, 2007, the licensee stated that it has performed a review of the control rod drive system scram time test results for Hatch 1 and 2. This review determined the following:

For Hatch 1, from 2002 to the beginning of cycle in 2006, Hatch 1 conducted a total of 1005 individual control rod scram tests. Out of those tests no control rods were identified as 'slow.'

For Hatch 2, from 2003 to the beginning of cycle in 2007, Hatch 2 conducted a total of 915 individual control rod scram tests. Out of those tests only two (2) control rods were identified as

'slow.'

The extensive histor ical database substantiates the claim of high reliability of the Hatch 1 and 2 control rod drive systems. The current TS, with TS Bases in SR 3.1.4.2, requires that 10 percent of the 137 control rods (or at least 15 rods) be tested via sampling every 120 cumulative days of operation in Mode 1. It also states that the sample remains representative if 20 percent or fewer of the control rods in the sample tested are found to be slow, per the criterion in TS Table 3.1.4-1.

This acceptance criterion will be re-defined for at-power surveillance testing from 20 percent to 7.5 percent when the surveillance period is extended to 200 cumulative days of operation in Mode 1.

This tightened acceptance criterion for at-power surveillance aligns with the TS 3.1.

4 requirement for the total control rods allowed to have scram times exceeding the specified limit. The revised bases submitted with the licensee's application shows that it has incorporated the revised acceptance criterion value of 7.5 percent into the TS Bases in accordance with its Bases Control Program.

The Nuclear Regulatory Commission (NRC) staff considers the extended surveillance interval to be justified by the demonstrated reliability of the control rod insertion system, based on historical control rod scram time test data, and by the more restrictive acceptance criterion for determining whether the sample of control rods tested remains representative. Therefore, the NRC staff finds the proposed TS change acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Georgia State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change surveillanc e requirements. The NRC staff has det ermined t hat the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (July 17, 2007, 72 FR 39084). Accordingly, the

amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is

reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: A. Jason Lising

Date: November 26, 2007 Edwin I. Hatch Nuclear Plant, Units 1 & 2

cc:

Mr. Dennis R. Madison Vice President - Hatch Edwin I. Hatch Nuclear 11028 Hatch Parkway North Baxley, GA 31513

Laurence Bergen Oglethorpe Power Corporation 2100 E. Exchange Place P.O. Box 1349 Tucker, GA 30085-1349

Mr. R. D. Baker Manager - Licensing Southern Nuclear Operating Company, Inc.

P.O. Box 1295 Birmingham, AL 35201-1295

Resident Inspector Plant Hatch 11030 Hatch Parkway N.

Baxley, GA 31531

Harold Reheis, Director Department of Natural Resources 205 Butler Street, SE., Suite 1252 Atlanta, GA 30334

Steven M. Jackson Senior Engineer - Power Supply Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW Atlanta, GA 30328-4684

Mr. Reece McAlister Executive Secretary Georgia Public Service Commission 244 Washington St., SW Atlanta, GA 30334

Arthur H. Domby, Esq.

Troutman Sanders Nations Bank Plaza 600 Peachtree St, NE, Suite 5200 Atlanta, GA 30308-2216

Chairman Appling County Commissioners County Courthouse Baxley, GA 31513

Mr. Jeffrey T. Gasser Executive Vice President Southern Nuclear Operating Company, Inc.

P.O. Box 1295 Birmingham, AL 35201-1295

Mr. K. Rosanski Resident Manager Oglethorpe Power Corporation Edwin I. Hatch Nuclear Plant P.O. Box 2010 Baxley, GA 31515