ML20205C161

Discusses GL 96-05 Issued on 960918 & Firstenergy 961118, 970317 & 980930 Responses to GL 96-05 Indicating Intent to Implement Provisions of JOG Program on MOV Periodic Verification at Perry Npp.Forwards RAI Re GL 96-05 Program

ML20205C161
Person / Time
Site:	Perry
Issue date:	03/25/1999
From:	Pickett D NRC (Affiliation Not Assigned)
To:	Myers L AFFILIATION NOT ASSIGNED
References
GL-96-05, GL-96-5, TAC-M97085, NUDOCS 9904010087
Download: ML20205C161 (7)

Text

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4***** 3 March 25, 1999 Mr. Lew W. Myers Vice President - Nuclear, Perry  :

FirstEnergy Nuclear Operating Company P.O. Box 97, A200 Perry, OH 44081

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 96-05 PROGRAM - PERRY NUCLEAR POWER PLANT, UNIT 1 (TAC NO.

M97085)

Dear Mr. Myers:

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 request that nuclear power plant licensees 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 performing their safety functions within the current licensing basis of the facility.

By letters dated November 18,1996 (PY-CEl/NRR-2114L), March 17,1997(PY-CEl/NRR-2142L), and September 10,1998 (PY-CEl/NRR-2318L), FirstEnergy responded to GL 96-05 Il indicating its intent to implement the provisions of a Joint Owners Group (JOG) Program on 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 f 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 Perry.

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= March 25, 1999 Attached is a request for additional information regarding the GL 96-05 program at Perry. As previously discussed with your staff, it is requested that you respond within 60 days of con oletion of the seventh refueling outage. It is our understanding that the seventh refueling is sch61 tad to begin on March 27,1999, and will last for approximately 35 days.

Sincerely.

Original signed by:

Douglas V. Pickett, Senior Project Manager Project Directorate 111-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-440

Enclosure:

As stated cc w/ encl: See next page Distribution Docket File PUBLIC PDill-3 R/F OGC TScarbrough JZwolinski GGrant, Rill ACRS i

DOCUMENT NAME: G:\PD3-3\ PERRY \97085LTR.WPD To recol.e e copy of this document, indcote in the box: "C" = Copy without enclosures *E" = Copy with enclosures "N" = No copy 0FFICE PM;PQIMr2 E LA:PDIII-2 E SC:EMEB D:PDIII-2 L ,

I4AME DPftYelt EBarnhill W DTerao* SRichards F DATE 03/23/99 03/2/99 03/02/99 03/as/99

• See Terao to Richards memo of 3/2/99 0FFICIAL RECORD COPY 1-  ;

March 25, 1999 Attached is a request for additional information'regarding the GL 96-05 program at Perry. As previously discussed with your staff, it is requested that you respond within 60 days of completion of the seventh refueling outage. It is our understanding that the seventh refueling is scheduled to begin on Marcti 27,1999, and will last for approximately 35 days. i

' Sincerely, Original signed by:

Douglas V. Pickett, Seninr Project Manager

' Project Directorate lll-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-440

Enclosure:

As stated cc w/ encl: See next page Rip _tt!bution Docket File PUBLIC

PDill-3 R/F OGC TScarbrough JZwolinski l GGrant, Rill ACRS l

DOCUMENT NAME: G:\PD3-3\ PERRY \97085LTR.WPD Ta receive a copy of this document, indicate in the box: "C" - Copy without enclosures "E" = Copy with enclosures "N" - No copy 0FFICE PM1EQ_IJ@ 2 E LA:PDIII-2 E SC:EMEB D:PDIII-2 E, ,

NAME DPfL*1(elt' EBarnhill ff,y- DTerao* SRichards F DATE 03/23/99- 03/2/99 03/02/99 03/.;ts/99

• See Terao to Richards memo of 3/2/99 0FFICIAL RECORD COPY b

~~ .

y C Attached is a request for additional information regarding the GL 96-05 program at Perry. As l previously discussed with your staff, it is requested that you respond within 60 days of completion of the seventh refueling outage,. It is our understanding that the seventh refueling is scheduled to begin on March 27,1999, and will last for approximately 35 days.

Sincerely,

_eg o_ v eM I Douglas V. Pickett, Senior Project Manager Project Directorate 111-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-440

Enclosure:

As stated cc w/ encl: See next page 1

1 1

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FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant, Units 1 and 2 cc:

Mary E. O'Reilly James R. Williams FirstEnergy Corporation Chief of Staff 76 South Main St. Ohio Emergency Management Agency Akron, OH 44308 2855 West Dublin Granville Road Columbus, OH 43235-2206 Resident inspector's Office U.S. Nuclear Regulatory Commission Donna Owens, Director P.O. Box 331 Ohio Department of Commerce -

Perry, OH 44081-0331 Division of Industrial Compliance Bureau of Operations & Maintenance Regional Administrator, Region lli .

6606 Tussing Road U.S. Nuclear R.egulatory Cominission P.O. Box 4009 801 Warrenville Road Reynoldsburg, OH 43068-9009 Lisle, IL 60532-4531 Mayor, Village of North Perry Sue Hiatt North Perry Village Hall OCRE Interim Representative 4778 Lockwood Road 8275 Munson North Perry Village, OH 44081 Mentor, OH 44060 Radiological Health Program Henry L. Hegrat Ohio Department of Health Regulatory Affairs Manager P.O. Box 118 FirstEnergy Nuclear Operating Company Columbus, OH 43266-0118 Perry Nuclear Power Plant P.O. Box 97, A210 Ohio Environmental Protection Perry, OH 44081 Agency DERR-Compliance Unit Lew W. Myers ATTN: Mr. Zack A. Clayton Vice President - Nuclear, Perry P.O. Box 1049 FirstEnergy Nuclear Operating Company Columbus, OH 43266-0149 P.O. Box 97, A200 Perry, OH 44081 Chairman Perry Township Board of Trustees Mayor, Village of Perry 3750 Center Road, Box 65 P.O. Box 100 Peny, OH 44081 Perry, OH 44081-0100 State of Ohio William R. Kanda, Jr., Plant Manager Public Utilities Commission FirstEnergy Nuclear Operating Company East Broad Street Perry N lear l'ower Plant Columbus, OH 43266-0573 P.O. Box 97, N306 Perry, OH 44081

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REQUEST FOR ADDITIONAL INFORMATION RESPONSE TO GENERIC LETTER 96-05 FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT DOCKET NO. 50-440

1. In NRC Inspection Report No. 50-440/96-05, the NRC staff closed its review of the motor-operated valve (MOV) program implemented at Perry Nuclear Power Plant (Perry) in response to Generic Letter tdL) 89-10, " Safety-Related Motor-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 term. For example, the inspectors noted that the licensee (1) agreed to modify valve 1G33-F040 during the next scheduled outage as part of Perry's margin improvement plan; (2) would continue to evaluate applicable information to confirm the valve factors applied to Anchor / Darling ficx-wedge gate valves 1E22-F012 and 1E51-F059 and Borg Wamer gate valve Groups 4 and 6; and (3) would monitor stem friction coefficient performance to improve the statistical basis and to confirm the stem friction coefficient assumptions applied to the closing direction thrust calculations. The licensee should describe the actions taken to address the specific long-term aspects of the MOV program at Perry noted in the NRC inspection report.

2. The JOG program specifies that the methodology and discrimination criteria for ranking MOVs according to their safety significance are the responsibility of each participating licensee. In its letter dated March 17,1997, the licensee stated that MOV risk ranking would be based, in part, on an expert review and Perry's Probabilistic Risk Assessment (PRA). As Perry is a boiling water reactor (BWR) nuclear plant, is the licensee applying the BWROG methodology for ranking MOVs based on their safety significance as 4 described in BWROG Topical Report NEDC-32264 and the NRC safety evaluation dated February 27,19967 If not, the licensee should describe the methodology used for risk l ranking MOVs at Perry in more detail, including a description of (1) the process used to develop sample lists of high-risk MOVs from other BWRs; and (2) how expert panels were used to evaluate MOV risk significance.

3. The licensee's interim static test program allows some valves with medium and high margin to be tested on a four or 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 ENCLOSURE

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• BWROG Topical Report NEDC-32719 describing the JOG program, the NRC staff 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 staff stated that this review must include both valve thrust (or torque) requirements and actuator output capability. The licensee should describe how its MOV static diagnostic testing program will satisfy this condition of the NRC safety evaluation.

4. 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 evaluation dated October 30,1997, on the JOG program, the NRC staff specified that -

licensees are responsible for addressing the thrust or torque delivered by the MOV motor actuator and its potential degradation. The licensee should describe the plan at Perry for ensuring adequate ac and de MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its Supplement 1.

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