ML061000038: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 14: Line 14:
| page count = 4
| page count = 4
| project = TAC:MC9617
| project = TAC:MC9617
| stage = Other
| stage = Approval
}}
}}


=Text=
=Text=
{{#Wiki_filter:April 20, 2006Mr. David A. ChristianSenior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
{{#Wiki_filter:April 20, 2006 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711


==SUBJECT:==
==SUBJECT:==
KEWAUNEE POWER STATION - CLARIFICATION CONCERNING RELIEFFROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE (REVISED RELIEF REQUEST VRR-05) FOR THE FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. MC9617)
KEWAUNEE POWER STATION - CLARIFICATION CONCERNING RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE (REVISED RELIEF REQUEST VRR-05) FOR THE FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. MC9617)


==Dear Mr. Christian:==
==Dear Mr. Christian:==


By letter dated January 23, 2006, Dominion Energy Kewaunee, Inc. (the licensee), submitted arequest for relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (the code). The revised Relief Request VRR-05 is for the Fourth 10-year inservice testing (IST) program interval at Kewaunee Power Station, which commenced on February 16, 2005. By letter dated March 24, 2006, the requested coderelief was granted pursuant to Title 10 of the Code of Federal Regulations, Part 50, Section50.55a(a)(3)(ii) based on the determination that (1) compliance with the specified Coderequirements results in hardship or unusual difficulty without a compensating increase in the level of quality and safety and (2) the proposed alternative provides reasonable assurance that the components are operationally ready. Following issuance, the Nuclear Regulatory Commission (NRC) staff was made aware of anerror in the supporting Safety Evaluation (SE). In Section 3.1.5 of the SE, the NRC staff statesthe following:Following the test, the enclosures need to be reassembled and leak tested inaccordance with [10 CFR Part 50] Appendix J. The additional activities involved with local observation are time consuming and performed in a Radiation Area. Therefore, the licensee proposes to perform the required local verification in conjunction with preventive maintenance on the valve motor operators, which is performed on a 36-month frequency. The NRC staff finds that requiring the licensee to meet the Coderequired frequency for local verification of valve position indication would result in a hardship without a compensating increase in the level of quality and safety.The error in the above text is that the licensee does not intend that the post-test leak testing ofthe valve enclosures be in accordance with Appendix J as documented in the licensee's January 23, 2006, application for Code Relief. In this regard, by way of clarification, the NRCstaff notes that the form of leak testing was not material to the issuance of the subject CodeRelief. Leak testing within a radiation area results in hardship or unusual difficulty regardless of D. Christian-2-whether such testing is performed in accordance with 10 CFR Part 50, Appendix J. Accordingly, the conclusions stated in the letter transmitting the Code Relief, dated March 24, 2006, and the associated SE, remain valid.Sincerely, /RA/L. Raghavan, ChiefPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-305 cc:  See next page
By letter dated January 23, 2006, Dominion Energy Kewaunee, Inc. (the licensee), submitted a request for relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (the code). The revised Relief Request VRR-05 is for the Fourth 10-year inservice testing (IST) program interval at Kewaunee Power Station, which commenced on February 16, 2005. By letter dated March 24, 2006, the requested code relief was granted pursuant to Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a(a)(3)(ii) based on the determination that (1) compliance with the specified Code requirements results in hardship or unusual difficulty without a compensating increase in the level of quality and safety and (2) the proposed alternative provides reasonable assurance that the components are operationally ready.
Following issuance, the Nuclear Regulatory Commission (NRC) staff was made aware of an error in the supporting Safety Evaluation (SE). In Section 3.1.5 of the SE, the NRC staff states the following:
Following the test, the enclosures need to be reassembled and leak tested in accordance with [10 CFR Part 50] Appendix J. The additional activities involved with local observation are time consuming and performed in a Radiation Area. Therefore, the licensee proposes to perform the required local verification in conjunction with preventive maintenance on the valve motor operators, which is performed on a 36-month frequency. The NRC staff finds that requiring the licensee to meet the Code required frequency for local verification of valve position indication would result in a hardship without a compensating increase in the level of quality and safety.
The error in the above text is that the licensee does not intend that the post-test leak testing of the valve enclosures be in accordance with Appendix J as documented in the licensees January 23, 2006, application for Code Relief. In this regard, by way of clarification, the NRC staff notes that the form of leak testing was not material to the issuance of the subject Code Relief. Leak testing within a radiation area results in hardship or unusual difficulty regardless of


ML061000038OFFICENRR/LPL3-1/PMNRR/LPL3-1/LANRR/CPTBNRR/LPL3-1/BC NAMEDJaffe:rsaTHarrisKPoertner*LRaghavan DATE4/20/064/19/064/18/064/18/06 Kewaunee Power Station cc:
D. Christian                                    whether such testing is performed in accordance with 10 CFR Part 50, Appendix J.
Resident Inspectors OfficeU.S. Nuclear Regulatory Commission N490 Hwy 42 Kewaunee, WI 54216-9510Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville RoadLisle, IL 60532-4351David ZellnerChairman - Town of Carlton N2164 County B Kewaunee, WI 54216Mr. Jeffery KitsembelElectric Division Public Service Commission of Wisconsin PO Box 7854 Madison, WI 53707-7854Mr. Michael G. GaffneyDominion Energy Kewaunee, Inc.
Accordingly, the conclusions stated in the letter transmitting the Code Relief, dated March 24, 2006, and the associated SE, remain valid.
Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216Mr. Chris L. FunderburkDirector, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711Mr. Thomas L. BreeneDominon Energy Kewaunee, Inc.
Sincerely,
Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216Ms. Lillian M. Cuoco, Esq.Senior Counsel Dominion Resources Services, Inc.
                                            /RA/
Millstone Power StationBuilding 475, 5th Floor Rope Ferry Road Waterford, CT  06385Plant ManagerKewaunee Power Station N490 Highway 42 Kewaunee, WI  54216-9511}}
L. Raghavan, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305 cc: See next page
 
ML061000038 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/CPTB                    NRR/LPL3-1/BC NAME DJaffe:rsa            THarris            KPoertner*     LRaghavan DATE      4/20/06          4/19/06            4/18/06        4/18/06
 
Kewaunee Power Station cc:
Resident Inspectors Office            Ms. Lillian M. Cuoco, Esq.
U.S. Nuclear Regulatory Commission     Senior Counsel N490 Hwy 42                           Dominion Resources Services, Inc.
Kewaunee, WI 54216-9510                Millstone Power Station Building 475, 5th Floor Regional Administrator, Region III    Rope Ferry Road U.S. Nuclear Regulatory Commission     Waterford, CT 06385 Suite 210 2443 Warrenville Road                  Plant Manager Lisle, IL 60532-4351                  Kewaunee Power Station N490 Highway 42 David Zellner                          Kewaunee, WI 54216-9511 Chairman - Town of Carlton N2164 County B Kewaunee, WI 54216 Mr. Jeffery Kitsembel Electric Division Public Service Commission of Wisconsin PO Box 7854 Madison, WI 53707-7854 Mr. Michael G. Gaffney Dominion Energy Kewaunee, Inc.
Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216 Mr. Chris L. Funderburk Director, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. Thomas L. Breene Dominon Energy Kewaunee, Inc.
Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216}}

Revision as of 21:10, 23 November 2019

Clarification Concerning Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (Revised Relief Request VRR-05) for Fourth 10-year Pump and Valve Inservice Testing Program
ML061000038
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 04/20/2006
From: Raghavan L
Plant Licensing Branch III-2
To: Christian D
Dominion Energy Kewaunee, Nuclear Management Co
jaffe D, NRR/DORL, 415-1439
References
TAC MC9617
Download: ML061000038 (4)


Text

April 20, 2006 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

KEWAUNEE POWER STATION - CLARIFICATION CONCERNING RELIEF FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE (REVISED RELIEF REQUEST VRR-05) FOR THE FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. MC9617)

Dear Mr. Christian:

By letter dated January 23, 2006, Dominion Energy Kewaunee, Inc. (the licensee), submitted a request for relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (the code). The revised Relief Request VRR-05 is for the Fourth 10-year inservice testing (IST) program interval at Kewaunee Power Station, which commenced on February 16, 2005. By letter dated March 24, 2006, the requested code relief was granted pursuant to Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a(a)(3)(ii) based on the determination that (1) compliance with the specified Code requirements results in hardship or unusual difficulty without a compensating increase in the level of quality and safety and (2) the proposed alternative provides reasonable assurance that the components are operationally ready.

Following issuance, the Nuclear Regulatory Commission (NRC) staff was made aware of an error in the supporting Safety Evaluation (SE). In Section 3.1.5 of the SE, the NRC staff states the following:

Following the test, the enclosures need to be reassembled and leak tested in accordance with [10 CFR Part 50] Appendix J. The additional activities involved with local observation are time consuming and performed in a Radiation Area. Therefore, the licensee proposes to perform the required local verification in conjunction with preventive maintenance on the valve motor operators, which is performed on a 36-month frequency. The NRC staff finds that requiring the licensee to meet the Code required frequency for local verification of valve position indication would result in a hardship without a compensating increase in the level of quality and safety.

The error in the above text is that the licensee does not intend that the post-test leak testing of the valve enclosures be in accordance with Appendix J as documented in the licensees January 23, 2006, application for Code Relief. In this regard, by way of clarification, the NRC staff notes that the form of leak testing was not material to the issuance of the subject Code Relief. Leak testing within a radiation area results in hardship or unusual difficulty regardless of

D. Christian whether such testing is performed in accordance with 10 CFR Part 50, Appendix J.

Accordingly, the conclusions stated in the letter transmitting the Code Relief, dated March 24, 2006, and the associated SE, remain valid.

Sincerely,

/RA/

L. Raghavan, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305 cc: See next page

ML061000038 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/CPTB NRR/LPL3-1/BC NAME DJaffe:rsa THarris KPoertner* LRaghavan DATE 4/20/06 4/19/06 4/18/06 4/18/06

Kewaunee Power Station cc:

Resident Inspectors Office Ms. Lillian M. Cuoco, Esq.

U.S. Nuclear Regulatory Commission Senior Counsel N490 Hwy 42 Dominion Resources Services, Inc.

Kewaunee, WI 54216-9510 Millstone Power Station Building 475, 5th Floor Regional Administrator, Region III Rope Ferry Road U.S. Nuclear Regulatory Commission Waterford, CT 06385 Suite 210 2443 Warrenville Road Plant Manager Lisle, IL 60532-4351 Kewaunee Power Station N490 Highway 42 David Zellner Kewaunee, WI 54216-9511 Chairman - Town of Carlton N2164 County B Kewaunee, WI 54216 Mr. Jeffery Kitsembel Electric Division Public Service Commission of Wisconsin PO Box 7854 Madison, WI 53707-7854 Mr. Michael G. Gaffney Dominion Energy Kewaunee, Inc.

Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216 Mr. Chris L. Funderburk Director, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. Thomas L. Breene Dominon Energy Kewaunee, Inc.

Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216