BSEP-98-0137, Forwards Addl Info in Response to 980701 Telephone Conference W/Nrc & Ineel.Addl Request for Relief for Impractical Testing Requirement Applicable to Primary Containment Vacuum Relief Valves,Included

Forwards Addl Info in Response to 980701 Telephone Conference W/Nrc & Ineel.Addl Request for Relief for Impractical Testing Requirement Applicable to Primary Containment Vacuum Relief Valves,Included

ML20237A563
Person / Time
Site:	Brunswick
Issue date:	08/06/1998
From:	Jury K CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20237A565	List: BSEP-98-0137, Forwards Addl Info in Response to 980701 Telephone Conference W/Nrc & Ineel.Addl Request for Relief for Impractical Testing Requirement Applicable to Primary Containment Vacuum Relief Valves,Included ML20237A571 ML20237A579
References
BSEP-98-0137, BSEP-98-137, TAC-MA1115, TAC-MA1116, NUDOCS 9808140182
Download: ML20237A563 (7)

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CP&L  !

C Ught Company P.O. Box 10429 Southport, NC 28461-0429 l

AUG 0 61998 SERIAL: BSEP 98-0137 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2  !

DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 INSERVICE TESTING PROGRAM PLAN FOR TillRD TEN-YEAR INTERVAL (NRC TAC NOS. mal 115.AND MAI116)

Gentlemen: ,

i By letter dated February 25,1998 (Serial: BSEP 98-0008), Carolina Power & Light (CP&L)

Company submitted the Inservice Testing Program Plan for the Brunswick Steam Electric Plant (BSEP), Unit Nos. I and 2, applicable to the third 10-year interval. The third 10-year j interval is common for BSEP, Unit Nos. I and 2, and began on May 11,1998.

The purpose of this letter is to: (1) provide additional information in response to a telephone conference between CP&L, NRC, and Idaho National Engineering and Environmental Laboratory (INEEL) that was held on July 1,1998, and (2) submit an additional request for relief  ;

for an impractical testing requirement applicable to the primary containment vacuum relief valves (i.e., Valve Relief Request VRR-1l). Information responding to the NRC request for  !

additional information is provided in Enclosures 1 through 7. Information' supporting Valve Relief Request VRR-11 is provided in Enclosure 8. To assist the NRC in the review of the Inservice Testing Program Plan, a revised list summarizing the applicable relief requests is provided in Enclosure 9. This list supersedes the information provided in Enclosure 1 of CP&L's letter dated February 25,1998.

Please refer any questions regarding this submittal to Mr. Warren J. Dorman, Supervisor -

Licensing, at (910) 457-2068.

Sincerely, a 4 8

. . 071 M-Keith R. Jury I Manager - Regulatory Affairs.

! Brunswick Steam Electric Plant 9008140182 980806 r PDR ADOCK 05000324 P PDR

Document Control Desk BSEP 98-0137 / Page 2 WRM/wrm j

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Enclosures:

1. Response To Request For Additional Information

2. Engineering Procedure OENP-16.7, " Administrative Control of the Check Valve Disassembly Program." Revision 10 i

3. Engineering Evaluation Report 92-0483, Revision 1

4. Cold Shutdown Justification CSJ-15 j

5. Valve Relief Request VRR-12

6. Valve Relief Request VRR '

7. Excerpt From NRC Letter dated January 4,1990, "Second Ten-Year Interval

inservice Testing Program - Brunswick Steam Electric Plant, Units 1 and 2 (TAC l )

' ' Nos. 63523 and 63524)"

8. Valve Relief Request VRR-11

9. Summary of Relief Requests for Third Interval Inservice Testing Program, Brunswick -

L Steam Electric Plant, Unit Nos. I and 2 l

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Document Control Desk .

BSEP 98-0137 / Page 3 cc (with enclosures):

' U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta,GA 30303 U. S. Nuclear Regulatory Commission ATTN: Mr. Charles A. Patterson, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. David C. Trimble, Jr. (Mail Stop OWFN 141122)

~ l1555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford

! Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Division of Boiler and Pressure Vessel North Carolina Department of Labor ATTN: Mr. Jack Given, Assistant Director of Boiler & Pressure Vessels 4 West Edenton Street

Raleigh, NC 27601-1092 i

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ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 INSERVICE TESTING PROGRAM PLAN FOR TillRD TEN-YEAR INTERVAL (NRC TAC NOS. MA1115 AND MAi116)

RESPONSE TO REOUEST FOR ADDITIONAL INFORMATION NRC REOUEST 1: .

1 To support review of the check valve disassembly and inspection portion of the In-service Testing Program, provide a copy of Engineering Procedure OENP-16.7.

CP&L RESPONSE:

A copy of Engineering Procedure OENP-16.7, " Administrative Control of the Check Valve Disassembly Program," Revision 10, is provided in Enclosure 2.

1 NRC REOUEST 2:

For Relief Request VRR-06 regarding the liigh Pressure Coolant Injection (IIPCI) system and I Reactor Core isolation Cooling (RCIC) system discharge check valves, provide either additional information supporting the similarityjustification or another alternative test. l l

CP&L RESPONSE:

Carolina Power & Light (CP&L) Company withdraws Relief Request VRR-06.

NRC REOUEST 3:

For Relief Request VRR-08, "IIPCI Check Valve Test," provide justification for the acceptance criteria associated with measurement of running torque rather than break-away torque. 1 CP&L RESPONSE:

Justification for the use of running torque rather than break-away torque is documented in Engineering Evaluation Report 92-0483, Revision 1, a copy of which is provided in Enclosure 3.

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I NRC REOUEST 4-Provide additional basis for Refueling Justification RFJ-04.

CP&L RESPONSE:

During the second 10-year Inservice Testing (IST) interval, Refueling Justification .RFJ-04 was classified as a Cold Shutdown Justification. Therefore, based on further review of Refueling

Justification RFJ-04, CP&L has determined that this item should be resubmitted as a Cold Shutdown Justification for the third 10-year IST interval. A copy of Cold Shutdown Justification CSJ-15 is provided in Enclosure 4 NRC REOUEST 5

Program Remark V-20 appears to be a deviation from the ASME Code; therefore, this item should be resubmitted as a relief request.

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CP&L RESPONSE:

Program Remark V-20 is being withdrawn and is being resubmitted as Valve Relief Request VRR-12. A copy of Valve Relief Request VRR-12 is provided in Enclosure 5.

NRC REOUEST 6:

Program Remark V-21 appears to be a deviation from the ASME Code. If this correct, please resubmit this item as a relief request.

CP&L RESPONSE:

Program Remark V-21 is being withdrawn and is being resubmitted as Valve Relief Request VRR-13. A copy of Valve Relief Request VRR-13 is provided in Enclosure 6.

NRC REOUEST 7:

Valve Relief R.equest VRR-02 does not follow the guidance contained in NUREG-1482,

" Guidelines for Testing Inservice Testing at Nuclear Power Plants;" therefore, the licensee is requested to provide additionaljustification for Valve Relief Request VRR-02.

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l l CP&L RESPONSE: j

, The relief requested by Valve Relief Request VRR-02, during the second 10-year IST interval,

! was approved by the NRC in a letter dated January 4,1990. A copy of the portion of the NRC l Safety Evt.luation applicable to the previously approved relief request is provided in Enclosure 7.

NRC REOUEST 8:

Valve Relief Request VRR-10 pertains to simulation of ambient temperature of the operating environment during set pressure testing. Correlations between operating and ambient temperatures have not been applied, as specified by ASME Code for Operations and Maintenance of Nuclear Power Plants (OM Code), Part 1. Provide additionaljustification to support the alternative testing being proposed. )

1 CP&L RESPONSE:

CP&L withdraws Valve Relief Request VRR-10.

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ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 INSE.RVICE TESTING PROGRAM PLAN FOR THIRD TEN-YEAR INTERVAL (NRC TAC NOS. mal 115 AND MAI116)

ENGINEERING PROCEDURE OENP-16.7. i

" ADMINISTRATIVE CONTROL OF THE l CilECK VALVE DISASSEMBLY PROGRAM." REVISION 10

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