ML20126H476
| ML20126H476 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/08/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8104140156 | |
| Download: ML20126H476 (3) | |
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 400 Chestnut Street Te m r II ter11 8, 1981
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Director of Nuclear Reactor Regulation g
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- {LE Attention:
Mr. A. Schwencer, Chief J
Licensing Branch No. 2 7
lf Division of Licensing 9
8y U.S. Nuclear Pegulatory Cmrnission p~
Washington, DC 20555 g
Dear Mr. Schwencer:
In the Matter of the Application of
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Docket Nos. 50-327 Tennessee Valley Authority
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Pursuant to the Sequoyah Nuclear Plant (SNP) license ccMition, DPR-77 its 2.c. (24), concerning cmpliance with Regulatory Guide 1.97, Fevinfon 2, UVA will provide a dctciled cchedule for ccepliance by June 30, 1981.
IVA initiatal a detailed progrcu of design evaluation for all of its nuclear plants in August 1979. 'Jhis pregram has reculted in the upgrMing of occiCent and status instruments to be used by control rom coerating nerconnel in assessment of plant and environs coMitions. These improvemnts in instrumentation have been defined on tle Sequoyah docket in WA's rceponses to the requirements of each of the following: tRTMr0578, MTAG-0505, tJJRIG-0068,13Tc2G-0654, tug-0596, aM tRmm-0737.
'ihese instrmentation im;rovtwnts related to Regulatory Guide 1.97 have ten or vill be incorporated into the SVP Pinal Safety Analysis Feport (FSAR) nM l
the StiP FMiological Mmrgency Plan.
She current ~tsulatory Culde 1.97 evaluation program for ST 19 a for-stp plan. She plan will (1) Coalesco the roq2irem^e.ts of the control room revievr (NUPJTc0700), the radiological cErgercy progran (MJFm-0696), the TMI-2 requirerrents (tamm-0737), aM the degradeo core tash force review; (2)
IndeixMently evaluate frm firnt prirciples the requirorent for type A, type B, type C, aM tyIn D variableer 5(=,
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1 Mr. A. Schwencer April 8,-1981 (3) Evaluate the current decign against Regulatory Guide 1.97r and (4) Ibtermine feasibility of ampliance with Regulatory Guide 1.97, Paision i
2, ircludirg cost aM rchedule.
An a result of our regulatory Guide 1.97 evaluation progren, w have developed une general and specific concernc. Wo brve been 5crking with the staff to recoIvo these conotrns. Generally, 'NA is concerned that we are properly resolving the apparent conflicts in requirements of Pegulatory Guido 1.97, Revision 2 and other IEC requircnents. WA fiMs that for the StD there are some PWR variables for which we might sed? an exception to the previctors aM c hedulce of the guide.-
Ecme exmples of our specific concerno about Tegulatory Guide 1.97,'Ibvision 2-requirements for S 2 unit 1 ares (1) Uhat are tM upgr*3e requirements for qualificilio, isolation, ambiguity, a M human factors? These requirewfb s $1d extensively inpact our achedule canmitments alroady ma6e.
(2) What are the schedulo requirencnts for irrplementodon for core thermocoupira, primnry contairrent isolation vahn position, primary ecolant radiation mmitors, and particulate aM halcgen rMiation rrnitors considering the difficulties ! pree remnt nM technical feasibility?
(3) W.at will the it: pact of a charge in radiological nource terms be? A potential change in cource terms should be esidered in the d~ialopment and procurement actions.
(4) Ect is the purp>so for both the reactor coolant level and core exit.
extended range variable being category 17 'these requirem3nts for crepry 1 appaar to irgmet the instanation schedule.
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3 Mr. A. fchwencer Aptil 8, 1981 We will continue to work with the NIC staff to resolve the n!nm corcerns before oar Jene 30, 1981 nuM.ittal.
If you hcVe cc:y qacstions, please get in touch with D. L. Intert at ns 857-2581.
Very truly yours, TDRES".Ef VAIEY Af7IHORITY L. M. Mills, elantoer Ntrieer 7krJulation ani Safety, Den M cubeceibw)
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