ML20235P389

Forwards List of Pressure Isolation Valves & Description of Periodic Tests or Measures Performed to Assure Integrity of Each Valve as Independent Barrier at RCPB in Response to Generic Ltr 87-06

ML20235P389
Person / Time
Site:	Rancho Seco
Issue date:	07/10/1987
From:	Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Miraglia F Office of Nuclear Reactor Regulation
References
GCA-87-200, GL-87-06, GL-87-6, NUDOCS 8707200470
Download: ML20235P389 (4)

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= SACRAMENTO MUNICIPAL UT!Li1Y DISTRICT D P. O. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA July 10, 1987 GCA 87-200 U. S. Nuclear Regulatory Commission Attn: Frank J. Miraglia, Jr.

Associate Director for Projects Philips Building 7920 Norfolk Avenue Bethesda, MD 20014 DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION LICENSE NO. DPR-54 RESPONSE TO GENERIC LETTER 87-06: PERIODIC VERIFICATION OF LEAK TIGHT INTEGRITY OF PRESSURE ISOLATION VALVES

Dear Mr. Miraglia,

The subject Generic Letter requested that licensees submit a list of pressure isolation valves together with a description of the periodic tests or other measures performed to assure the integrity of each valve as an independent barrier at the reactor coolant pressure boundary. For each test listed, the submittal should include the acceptance criteria for leakage, operational limits and the frequency of test performance. The District hereby provides this information.

Attachment 1 to this letter contains a list of the pressure isolation valves as defined in Generic Letter 87-06. It is understood that this only applies where the reactor coolant system is connected to low-pressure safeguard systems or other low-pressure syttems that penetrate primary containment and does not include valves downstream of flow restricting orifices or small piping. Attachment 2 contains a brief description of the tests used to check the seat integrity of the valves listed in Attachment 1. It includes the acceptance criteria and frequency of each.

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t 8 I I RANCHO SECO NUCLEAR GENERATING STATION D 1444o Twin Cities Road, Herald, CA 95638 9799;(2o9) 333-2935

'iCA 87-200 Frank J. Miraglia, Jr. July 10, 1987 4

The Generic Letter referred to an order dated April 20,1981, (Event V l

Order), which required older plants to leak test certain specific pressure isolation valves on an individual basis. The pressure isolation valves listed in the order are RCS-001, RCS-002, DHS-015 and DHS-016. The requirements of this order have been incorporated into the Rancho Seco Technical Specifications.

Should you or your sttff have any questions, please contact Karl Meyer at (916) 452-3211, extension 4721.

Sincerely,

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Carl Andognini Chief Executive 0 ficer, Nuclear i

Attachments cc: G. Kalman, NRC, Bethesda (2)

A. D'Angelo, NRC, Rancho Seco l

-ATTACHMENT 1-

-A' .

< CONNECTED LOW OPERATIONAL VALVE PRESSURE SYSTEM FUNCTION TEST LIMITS' j J

RCS-001 DHS/CFS ECCS Check Valve SP.203.11

-RCS-002 DHS/CFS ECCS Check Valve SP.203.11 DHS-015 DHS/CFS ECCS Check Valve SP.203.11 l DHS-016 PHS/CFS ECCS Check Valve SP.203.11 i CFS-001 CFS ECCS Check Valve SP.203.11 CFS-002 CFS ECCS Check Valve -SP.203.11 HV-20001 DHS DH Suction Containment Iso. SP.19 (1) j HV-20002 DHS DH Suction Containment Iso. SP.19 (1)

DHS-059 DHS/CFS Aux. Spray Check Valve None HV-26011 DHS/CFS Aux Spray Isolation None SFV-22023 PLS Letdown Containment Iso. SP.422A (2) ]

SFV-22009 PLS Letdown Containment Iso. SP.422A (2) j SFV-24004 PLS Seal Return Contain. Iso. SP.422A (2)

SFV-24013 PLS Seal Return Contain. Iso. SP.422A (2)

Notes: (1) Close interlock at 255 psig RCS pressure (2) Close on Safety Features Actuation l

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, ATTACHMENT 2 o- SP.203.11: " Decay Heat / Core Flood. Systems Stop Check / Check Valve Seat Integrity Surveillance Test"-

Acceptance Criteria: 'S gpm (each valve) subject to limits of Rancho Seco Technical Specifications Frequency: Quarterly at Cold Shutdown

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SP.19: " Refueling Internal Seat Integrity Surveillance Test for Decay Heat Drop Line Valves Acceptance Criteria: 1 gpm each valve Frequency: Refueling Interval SP.422A: " Local Component Leak Rate Surveillance Testing" Acceptance Criteria: Guideline is 400 sccm for the letdown valves and 800 secm for the seal water return valves. Note: Valves are tested per.10 CFR 50 Appendix J. Limit is l

106,000 sccm for all penetrations combined.

Frequency: Refueling Interval 4

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