ML20090E301
| ML20090E301 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/02/1992 |
| From: | Parker T NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9203090360 | |
| Download: ML20090E301 (3) | |
Text
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Northom States Power Company 414 Ni<;ollet Mall (AnneagM. Minosota 55401 192#
Teghone (8 t 2) 330 5%0 March 2, 1947 10 CFS Part 50 Section bO,5$a(g)
US :1uclev Regubtory Co umission Attn.
Document Corttrol Desk
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Washington DC 20'.55 WAIRIE 1SIANE MJCLEAR GENERATING PLANT Docket Nos. 50 232 laceuse Nos. DPR-42 50 306 DPR-60 Enlief Hnquent No. 70 S.L pnd Ten-Year _1tum.dri. lng.p,ge t ion Intervd NRC Staff review and approvr.1 is bein6 raquested for Request for Relitf No.
70, f rom the requircunts of the ASME IMiler und Presmurc Vessel Code, Sect on i
XI, Inservice Inspection, as gecified in the Prairie Island InservN inspe.ction and Testing Pre:; ram for the Second Ten Year T.nterval.
This program was submitted to the Comnilasion on Decemboi 30, 1983 and approvad by the NRC Staff ou December 26, 1984.
This Knlof Request is being submitted in accorciance wit'n 10 CiR Part 50, fection 50.35a(g)(6)(1).
Relief 1s being requested from the Code %st frequency reruf rementa for safety inject. ion to reactor vessal valve, ESI-26-1, a Code Class 1. valve The 1980
'Vinter 1981. Addanda or the ASME Code requires relief valu e. leu tested
- t a five year interval.
This valve is scheduled to be tested during, the current refueling outage.
The plant condition necessary to teet this valve requtres removal of one train of kHR from service. With the increased awareness of the need for RllR availability, the plant believes this should be done during a full core affload. Therefore, this relief request proposes to change t5e testing frequency from every five years to when the core is unloadW, but not morr f requently than once every rivo years.
This will test the valvo at least every tan years as the core is unloaded for the 10 year hydro t est.
The valve was teste.d during the lact core offload in Sy euber 1985, The valve functioned satisfactorily. The next core officad is scheduled for 1995 or 199f,.
The five yes,e test of this valve is scheduled for this outage, so rel:e" is needed by March 11, 1992.
heatup is scheduled to commence on March 12, 1992.
We apologize for requesting relief from the ASME Crvie at this late date.
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b 9203C9036'? 920302 1
PDR APO^% 15000282 G
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Northern States Power Company NRC Lettet.'
March 2, 1992 Page 2 Relief Request No 70 is rpplicable to Prairie Island-Unit 2 only.
Pralrlo i
Island Unit I las t. tented :be Safety Injection to Reactor Vecsol Relief Valve in 1991 and t e 1986 Code requirements will be in et'fect prict to the next h
scheduied test.
Since, the 198d edition of the ASME Code requires testing of Code Class 2 reitef valves every 10 vears, no chsnge is needed for Unit 1.
Please contac* us if you have any questions related.to this Relief Request.
J Jtb 4 g; nmas ta fer Nanager f-Nuclear Support-1.crvices c: Regional A,hainistrator III, NRC NRR Project Manager, NRC
-PRC Renident Inspector
,itate of Minnesota Hartford Insurance J Silberg
.Attac%nent:
Relief Requesc No. 70 Unit 2 i
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REQUEST FOR RELIEF, 4 ~
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'ASME' COMPONENT--
. FUNCTION CODE VA1.VE '
s CIASC CAT 2S1-26.-1 RHR Vessel inject; ion. Relief Valve -
Protects Ri!R heat exchanger supply line 2
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to vessel:from overpressure q
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CODE REOUIRFME q
- s The relief valve 'setpoint; will not be. tested at the frequency required by liJV-3511 in the 1980 Winter 1981 Addenda' of '
'the ASME Code.
BASIS i
.. t To test this valve's setpoint either by testing in place cr bench testing. requires removing one loop of the R12 system l
from service. - The kHR system is necessary for safe plant. operation during.all-modes of reactor operation except whet -
the reactor core is' unloaded. To maintain RifR reliability and safely test this valve., fuel should not be in the reactor-vessel.
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The core is unloaded every ten, years for the hydro. This valve was tested during the last cote effload in September 1935. 3e valve. functioned satisfactorily. The - next core offload is scheduled for 1995 or 1.996.
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The 1986 ASME Code requires this valve to be tested once per 10 years. The Third Ten Year Interval Inservice Testing I
Prograra begins in December 1994. and will be updated to 1986. Code.
I Unit: I has an identical valve perfcrming the same function. The Unit i valve was last tested in 1991. and functioned i
satisfactorily.
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ALTERNATE INSPECTION'(TESTINC):
The valve vill be tested when the core is unloaded, but not more frequently than once every five years.
SCHEDULE FOR IMPLEMENTATION
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1992 Refueling outage.
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PI 151/IST Section 2.5-45 2nd 10-YR PROGRAM 3/2/92..
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