ML20207E040

Forwards Request for Addl Info Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, Program at Prairie Island Nuclear Generating Plant

ML20207E040
Person / Time
Site:	Prairie Island
Issue date:	03/04/1999
From:	Kim T NRC (Affiliation Not Assigned)
To:	Richard Anderson NORTHERN STATES POWER CO.
References
GL-96-05, GL-96-5, TAC-M97089, TAC-M97090, NUDOCS 9903100135
Download: ML20207E040 (4)

Text

. s March 4, 1999 Mr. Roger O. Anderson, Director Nuclear Energy Engineering Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 96-05 PROGRAM AT PRAIRIE ISLAND NUCLEAR GENERATING PLANT (TAC NOS. M97089 AND M97090)

Dear Mr. Anderson:

On September 18,1996, the NRC issued Generic Letter (GL) 96-05, " Periodic Verification of Design Basis Capability of Safety Related Motor-Operated Valves," to re-quest that nuclear power plant licensses establish a program, or ensure the effectiveness of the current program, to verify on a periodic basis that safety-related motor-operated valves (MOVs) continue to be capable of perforrning their safety functions within the current licensing basis of the facility.

On March 17,1997, Northern States Power Company (NSP) submitted a response to GL 06-05 indicating its intent to implement the provisions of a Joint Owners Group (JOG) Program e :

MOV Periodic Verification. The NRC staff has encouraged licensees to participate in the industry-wide JOG program to provide a benefit in reactor safety by sharing expertise and information on MOV performance and to increase the efficiency of GL 96-05 activities at nuclear plants. Licensee participation in the JOG program also minimizes the amount of information necessary for the NRC staff to review each licensee's response to GL 96-05. As a result, the NRC staff requires only limited information to complete its GL 96-05 review for Prairie Island.

Enclosed is a request for additional information regarding the GL 96-05 program at Prairie Island. As agreed upon in a March 3,1999, teleconference with Mr. Jeff Kivi of your staff, your response is expected within 60 days of the date of this letter. If you have any questions regarding this matter, please contact me at (301) 415-1392.

! Sincerely,

, ORIGINAL SIGNED BY Tae Kim, Sr. Project Manager Project Directorate Ill-1 '

Division of Licensing Project Management

' Office of Nuclear Reactor Regulation Docket Non 50-282 and 50-306 Enclosure. as stated cc w/ encl: See next page DISTRIBUTION: '

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• Prairie Island Nuclear Generating Mr. Roger O. Anderson, Director Northern States Power Company Plant cc:

J. E. Silberg, Esquire Site Licensing Shaw, Pittman, Potts and Trowbridge Prairie Island Nuclear Generating 2300 N Street, N. W. Plant Washington DC 20037 Northern States Power Company 1717 Wakonade Drive East  ;

Plant Manager Welch, Minnesota 55089 Prairie Island Nuclear Generating Plant Tribal Council Northern States Power Company Prairie Island Indian Community 1717 Wakonade Drive East ATTN: Environmental Department Welch, Minnesota 55089 5636 Sturgeon Lake Road i Welch, Minnesota 55089 Adonis A. Nebiett Assistant Attorney General Office of the Attorney General 455 Minnesota Street Suite 900 St. Paul, Minnesota 55101-2127 6

U.S. Nuclear Regulatory Commission Resident inspector's Office 1719 Wakonade Drive East Welch, Minnesota 55089 9642 Regional Administrator, Region ill U.S. Nuclear Regulatory Commission

^

801 Warrenville Road Lisle, Illinois 60532-4351 Mr. Stephen Bloom, Administrator Goodhue County Courthouse I Box 408 l Red Wing, Minnesota 55066-0408 Kris Sanda, Commissioner Department of Public Service 121 Seventh Place East Suite 200 i St. Paul, Minnesota 55101-2145 )

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's REQUEST FOR ADDITIONAL INFORMATION ON RESPONSE OF  :

! PRAIRIE ISLAND NUCLEAR GENERATING PLANT TO GENERIC LETTER 96-05 L

! 1. In NRC Inspection Report No. 50-282 & 306/95010, the NRC staff closed its review of the

! motor-operated valve (MOV) program implemented at Prairie Island Nuclear Generating

! Plant (Prairie Island) in response to Generic Letter (GL) 8910, " Safety-Related Motor-i Operated Valve Testing and Surveillance." In the inspection report, the NRC staff ,

discussed certain aspects of the licensee's MOV program to be addressed over the long i term. For example, the inspectors noted that the licensee (1) intended to modify the Unit 1

l power-operated reilef valve (PORV) block valve during the next refueling outage;

} (2) plenned to revise the documented design-basis differential pressures for the PORV l

block valves to reflect the PORV reset pressure; (3) planned to either conduct future l dynamic tests with diagnostics or apply the Electric Power Research Institute (EPRI) MOV

Performance Prediction Model (PPM) to four valve groups (Pows:1 solid-wedge gate i valves, Powell globe valves, Crane gate valves, and Velan gate valves); and (4) was

! expected to consider including a margin for valve degredations in its setup calculations.

The licensee should describe the actions taken to address the specific long-term aspects j of the MOV program at Prairie Island noted in the NRC inspection report.  ;

j 2. In a letter dated March 17,1997, the licensee stated that it is participating in the Joint

! Owners Group (JOG) Program on MOV Periodic Verification in response to GL 96-05. On l August 12,1997, the Westinghouse Owners Group (WOG) submitted Revision 2 of 1 1

i Topical Report MPR-1807, " Joint BWR, Westinghouse and Combustion Engineering

Owners Group Program on Motor-Operated Valve (MOV) Periodic Verification." On

October 30,1997, the NRC staff completed a safety evaluation concluding that the JOG

program is an acceptable industry-wide response to GL 96-05, with certain conditions and

! Umitations. The licensee should update its commitment to the JOG program to address j Revision 2 of the JOG topical report and the NRC safety evaluation.

l 3. Is the licensee applying the Westinghouse Owners' Group (WOG) methodology for i ranking MOVs based on their safety significance as described in WOG Engineering Report V EC-1658 A (Revision 2, dated August 13,1998)," Risk Ranking Approach for Motor-Operated Valves in Response to Generic Letter 96-05," and the NRC safety evaluation ,

dated April 14,1998, on Revision 1 of WOG Engineering Report V-EC-1658-A? If not, the l licensee should describe the methodology used for risk ranking MOVs at Prairio Island in more detail, including a description of (1) the process used to develop sample lists of high risk MOVs from other Westinghouse plants; and (2) how expert panels were used to evaluate MOV risk significance.

4. The licensee's interim static test program allows some valves with medium and high margin to be tested on a four and six refueling outage frequency, respectively. This is consistent with the outage frequency recommended by the JOG interim static diagnostic test program. However, in the NRC safety evaluation dated October 30,1997, on WOG Topical Report MPR 1807 describing the JOG program, the NRC stated that MOVs with scheduled test frequencies beyond 5 years will need to be grouped with other MOVs that will be tested on frequencies less than 5 years in order to validate assumptions for the longer test intervals. The NRC stated that this review must incluoe both valve thrust (or torque) requirements and actuator output capability. Tne licensee should describe how its )

MOV static diagnostic testing program will satisfy this condition specified in the NRC safety evaluation.

l Enclosure  :

)

i

e 8 . 2- l S. The JOG program focuses on the potential age-related increase in the thrust or torque required to operate valves under their design-basis conditions. In the NRC safety l evaluation dated October 30,1997, on the JOG program, the NRC staff specified that licensees are r.1sponsible for addressing the thrust or torque delivered by the MOV motor actuator and its potential degradation. The licensee should describe the plan at Prairie Island for ensuring adequate ac and de MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its~

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