ML20202G248
| ML20202G248 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/03/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Campbell G ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8607150348 | |
| Download: ML20202G248 (3) | |
Text
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((pd July 3, 1986 Docket No. 50-313 Mr. Gene Campbell Vice President, Nuclear Operation Arkansas Power and Light Company P. O. Box 551' Little Rock, Arkansas 72203
Dear Mr. Campbell:
We have recently been discussing with your people our concerns about the fact that Arkansas Nuclear One, Unit 1, does not currently have the PORV and block valve in the ANO-1 Inservice Test Plan or included in the Technical Specification surveillance requirements. However, we understand that now you have decided to include the PORV and the block valve in the IST plan.
Enclosed is our position on the surveillance requirements of the PORV and block valve. We request that you implement this position into your current IST program and provide us with the addition to the IST program for our review.
We request your schedule for doing this within 30 days on receipt of this letter.
The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, 0MB clearance is not required under P.L.96-511.
Sincerely, or%t nmas y John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B
Enclosure:
As stated cc w/ enclosure:
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Mr. G. Campbell Arkansas Power & Light Company Arkansas Nuclear One, Unit I cc:
Mr. J. Ted Enos Manager, Licensing Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 Mr. James M. Levine General Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Mr. Nicholas S. Reynolds Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.
Washington, D.C.
20036 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Marylend 20814 Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Frank Wilson, Director Division of Environmental Health Protection Department of Health Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72201 Honorable William Abernathy County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801-
}
NRR POSITION ON IST OF PORV AND BLOCK VALVE MAY 28, 1986 On the basis of its functions, PORVs should be tested in accordance with Section XI requirements for Category B/C valves. As such, the Code requires setpoint, stroke and stroke time testing (paragraphs IWV-3410 and 3510 of Section XI). The PORV block valves should be designated as Category A type valves which require leak rate, stroke and stroke time testing in accordance with paragraphs IWV-3410 and 3420 of Section XI.
Listed below i
are the testing schedules for P0PVs and PORY block valves consistent with the ASME Code requirements.
PORVS:
1.
As permitted in ASME Section XI, paragraph IWV-3412(a) for valves for which it is not practical to exercise during plant operation full stroke exercising should be performed at each cold shutdown, or, as a minimum, once each refueling cycle.
2.
Stroke timing should also be performed at each cold shutdown, or, as a minimum, once each refueling cycle.
1 3.
Fail safe actuator testing should also be performed at each cold shutdown, or, as a minimum, once each refueling cycle.
4.
Set point testing should be performed every refueling outage.
PORV Block Valves:
1.
Full stroke exercising and stroke timing should be performed at the normal Code specified 3 month interval.
2.
Leak testing should be performed every 2 years.
In addition, the preparation of a specific industry standard for inservice j
testing of PORVs is nearing completion.
The standard is 0M-13, " Requirements for Periodic Performance Testing and Monitoring of Power Operated Relief Valves."
d The standard will contain testing requirements similar to those listed above.
l In addition, as an alternate to stroke testing of the PORV on the pressurizer, it would-permit testing, once each fuel cycle, at fluid flow conditions the same as those in the reactor coolant system, at a steam test facility.
It is expected that OM-13, after final publication will ultimately be referenced in ASME Section XI.
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