ML16131A463

Forwards Request for Addl Info Re Proposed pressure-temp Limits Review

ML16131A463
Person / Time
Site:	Oconee
Issue date:	09/07/1993
From:	Wiens L Office of Nuclear Reactor Regulation
To:	Hampton J DUKE POWER CO.
References
TAC-M87112, TAC-M87113, TAC-M87114, NUDOCS 9309150195
Download: ML16131A463 (4)

Text

Sepomber 7, 1993 Docket Nos. 50-269, 50-270 DISTRIBUTION and 50-287 Docket File EWang NRC/Local PDRs JTsao Mr. J. W. Hampton PDII-3 Reading OGC Vice President, Oconee Site SVarga ACRS (10)

Duke Power Company GLainas LWiens P. 0. Box 1439 DMatthews Seneca, South Carolina 29679 LBerry EMerschoff, RII

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING PROPOSED PRESSURE TEMPERATURE LIMITS REVIEW - OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 (TAC NOS. M87112, M87113, AND M87114)

The NRC staff is reviewing your application dated July 14, 1993, as supplemented August 24, 1993, for proposed amendments to the Oconee Technical Specifications concerning Pressure-Temperature limits. We find that further information, as indicated in the enclosure, is required to complete our review. Your response to the enclosed questions is requested within 30 days of the date of this letter. If you have any questions regarding this matter, please contacted me at (301) 504-1495.

This requirement affects fewer than ten respondents, therefore, it is not subject to Office of Management and Budget review under P.L.96-511.

Sincerely,

/s/

L. A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects -

I/II Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional Information cc w/enclosure:

See next page OFFICE PDII-3 PDII-3P P)

-3/ M PD P01

/

DAE L.BERRY E.WANG

____ENS D.MATTHEWS DATE

/

93

/-3/93 9'/'/93

/1/93 OFFICIAL RECORD COPY FILE NAME:.G:\\OCONEE\\RAI-PT.LTR 9309150195 930907 C

L C

t PDR -ADOCK 05000269 P

PDR

tpkREGj 0

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Docket Nos. 50-269, 50-270 September 7, 1993 and 50-287 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, South Carolina 29679

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERNING PROPOSED PRESSURE TEMPERATURE LIMITS REVIEW - OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 (TAC NOS. M87112, M87113, AND M87114)

The NRC staff is reviewing your application dated July 14, 1993, as supplemented August 24, 1993, for proposed amendments to the Oconee Technical Specifications concerning Pressure-Temperature limits. We find that further information, as indicated in the enclosure, is required to complete our review. Your response to the enclosed questions is requested within 30 days of the date of this letter. If you have any questions regarding this matter, please contacted me at (301) 504-1495.

This requirement affects fewer than ten respondents, therefore, it is not subject to Office of Management and Budget review under P.L.96-511.

Sincerely, L. A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects -

I/Il Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional Information cc w/enclosure:

See next page

Mr. J. W. Hampton Duke Power Company Oconee Nuclear Station cc:

Mr. A. V. Carr, Esquire Mr. M. E. Patrick Duke Power Company Compliance 422 South Church Street Duke Power Company Charlotte, North Carolina 28242-0001 Oconee Nuclear Site P. 0. Box 1439 J. Michael McGarry, III, Esquire Seneca, South Carolina 29679 Winston and Strawn 1400 L Street, NW.

Mr. Alan R. Herdt, Chief Washington, DC 20005 Project Branch #3 U. S. Nuclear Regulatory Commission Mr. Robert B. Borsum 101 Marietta Street, NW. Suite 2900 Babcock & Wilcox Atlanta, Georgia 30323 Nuclear Power Division Suite 525 Ms. Karen E. Long 1700 Rockville Pike Assistant Attorney General Rockville, Maryland 20852 North Carolina Department of Justice Manager, LIS P. 0. Box 629 NUS Corporation Raleigh, North Carolina 27602 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Mr. G. A. Copp Licensing -

EC050 Senior Resident Inspector Duke Power Company U. S. Nuclear Regulatory Commission P. 0. Box 1006 Route 2, Box 610 Charlotte, North Carolina 28201-1006 Seneca, South Carolina 29678 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 County Supervisor of Oconee County Walhalla, South Carolina 29621

• g 0

REQUEST FOR ADDITIONAL INFORMATION On July 14, 1993, Duke Power Company submitted proposed technical specification changes concerning the Pressure-Temperature (P-T) limits for staff review. On August 24, 1993, the licensee submitted additional information in support of staff review. BAW-2166, "B&W Owners Group Response to Generic Letter 92-01" was referenced in the August 24, 1993, letter.

After reviewing the above documents, the staff requests the following additional information for each Oconee unit:

1.

Identify the limiting material used in P-T limits. BAW-2166 identified the limiting material for upper shelf energy but not for RT Table 10 in BAW-2166 provided a semblance of limiting materials; owever, the RTNDT calculation was at the capsule fluence, not at the fluence of P-T limits.

2.

In the August 24, 1993, letter, the licensee provided fluence values for the P-T limits in each unit; however, the staff was not able to verify the fluence values in the letter with respect to surveillance data from Oconee capsule reports or BAW-2166 (pages 5-6 to 5-9).

Provide references and page numbers where the fluence values in the August 24, 1993, letter were obtained. If the fluence values were derived from some other values, provide the derivation. Also, provide a table similar to Table 5.2-1 on pages 5-6 to 5-9 in BAW-2166 that show fluences for each beltline material at the requested effective full power years.

3.

For each of the RT shown in the August 24, 1993, letter, provide the initial RT, shifPiWTRT and margin. For the shift RTNDT calculation, provide the chemistry actor and fluence factor. If the chemistry factor is calculated based on surveillance data, provide measured shift in RT T and corresponding fluence factor. The staff recommends a formaf that resembles Table 8-1 on page 8-4 of BAW-2128, Revision 1.

BAW-2128 is the surveillance report for Capsule OCIII-D removed from Oconee Unit 3.

4.

Provide heatup and cooldown rates for (1) normal operation, and (2) inservice leak and hydrostatic test. In the July 14, 1993, submittal, heatup and cooldown rates were neither identified in the proposed P-T curves nor in the proposed amendment text.