ML17324B263

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Forwards SER & Technical Evaluation Rept EGG-NTA-7458 on Generic Ltr 83-28,Item 4.5.2 Re Online Testing of Reactor Trip Sys,Including Independent Testing of Undervoltage & Shunt Trip Attachments.Action Complete
ML17324B263
Person / Time
Site: Beaver Valley, Catawba, Byron, Braidwood, Diablo Canyon, Callaway, Cook, Comanche Peak, 05000000
Issue date: 03/03/1987
From: Youngblood B
Office of Nuclear Reactor Regulation
To: Dolan J
AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
Shared Package
ML17324B264 List:
References
GL-83-28, NUDOCS 8703090104
Download: ML17324B263 (1)


Text

Docket Nos.:

50-315 and 50-316

~ MAR 1S87 Mr. John Dolan, Vice President Indiana and Michigan Electric Company c/o American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43216

Dear Mr. Dolan:

By letter dated November 4, 1983, the Indiana and Michigan Electric Company responded to Generic Letter 83-28 for the Donald C.

Cook Nuclear Plant, Unit Nos.

1 and 2.

In that letter, IMEC addressed item 4.5.2, among other things, which requires on-line testing of the Reactor Trip System including independent testing of the undervoltage and shunt trip attachments.

We have completed our review, and our contractor's Technical Evaluation Report and our Safety Evaluation Report are attached.

We find the IMEC meets the requirements of item 4.5.2, and this action is complete.

Generic Letter 83-28 also addresses in item 4.5.3 the intervals for on-line functional testing of the Reactor Trip System.

IMEC has referenced in the April 10, 1985 letter the WCAP-12071 for guidance in establishing these intervals.

(AEP:NRC 0838H)

In a letter dated February 21, 1985 from Cecil Thomas to J.J.

Shepard, WOG, the NRC found acceptable the reference to WCAP 10271 "Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System," but only for analog channels.

(We believe the IMEC reference to WCAP 12071 is actually to WCAP 10271).

We further stated in the February 21, 1985 letter that NRC review of the changes proposed for the actuation logic and reactor trip breakers has been deferred, i.e., more effort would be needed to integrate the requirements of Item 4.5.3 into WCAP 10271.

We request that IMEC establish a current..position on Item 4.5.3 and inform this office at the earliest convenience.

Sincerelyis B.J.

Youngblood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A

Enclosure:

Safety Evaluation Report Technical Evaluation Report cc:

See next page DISTRIBUTION:

Docket File nlgg IIRN4 R

dt EJordan JPartlow

  • SEE PREVIOUS CONCURRENCE Local PDR NRC PDR BJYoungblood Reading EJordan MDuncan ACRS(10)

BGriems PWR¹4/DPWR-A PWR¹4/DPWR-A

  • DWigginton/rad
  • MDuncan 02/24/87 02/24/87 8703090104 870303 PDR ADOCK 05000315, E

PDR FOB/DPWR-A FRosa 02/28'/87 PW R-A BJ o g lood 0 /

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