IR 05000317/1975023
| ML19323F660 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs, Crane  |
| Issue date: | 12/08/1975 |
| From: | Nolan F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Brunner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8005290294 | |
| Download: ML19323F660 (2) | |
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s s-UNITtO STATES NUCLLAR R EG U L A TOR Y CO f IT.1lS S IO N
W A S HIN C 10 rd. o. C. 2 0 5 5 5
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DEC 0 0 0 1
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s E. J. Prun wr, Chief, "cactor Operations Erar,ci, i?
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BALTI' h!' ':A: ! Jib ELECT.IIC CO.,
CALVtRT CLIFFS 1 (AITS F14192Hl)
Yhe subject
. brief indication of ti e status of thesememorandua identified
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v ' sJ general cou ents relatin items and sore
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to the inspection findin:;s,
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neport !o. 50-317/
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- randu 1 rendinc p.v',ed Technical Specification changedated 12/8/75, J. 9. S
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Item 2:
in wr m nefini tion o f :;c::ty-Related ences i. h :i.n, the itccs Because of the differ-
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facility: h u wr, t ideatified c.ay differ for each specific
- cneral defin; tion is as follor,
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features, and functions affecting those plant am features, which:
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will be under nerral plantrelied upon far safe shutdown and cooldoim of the reactor condition for..nentended shutdown period, erconditions and for ma safe 2.
will Le relied upon for safe shutdotm and cooldoun of the
under fa titeri, upset, reactor the reactor in a safe condition for an extended shutdor erer:;ency condit
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own period, or-mi 3.
uill bn or lir.itin conditionstolled upon for establishing confor:4ance with saf t
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e y lir:its gecificaticas, orfor operatica that are included in the facility technicn!
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are claa.ified as engineered safety features or will be reli d
to nuro:t o r ar. :re e upon
..ithin 6,i a liiiita, the operaticas of engineered safety features
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t,ill bc
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E. J. Brunner-2-DEC 0 S 1375 a
b Item 3:
Regulatory Guide, "Muclear Power Plant StructuresThis item was i %,,
w-ow and Activities Subject
, Systems, Components to Quality Assurance Program."
A review o! the Inspection Report No. 50-317/75-23 revealed that a citation v.u issued to the licensee because reactor coolant, water, an< diesel fuel were excluded from the QA Program bora ted discussed in the report indicated that Information
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identified ca the "Q" Lint of Safe ty-itelated Itemsthese items were not specifically (approved) ay the "Q" Lis t unich had been reviewed Committee.
In addition, information discussed in the FS R Section 1.c., Quality Assurance Progra-for the Operations
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Ph a.ce, does identify the specific items that not List; however, we note tha t should be on the "Q" specific surveillance requirements for the three itcas identified abth
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,D 46 Based on the foregoing, it appears that
. ?,d nique by cit in;; t!m licensee IE employed a ratcheting tech-for failure to include specific items on the "Q" Li:,t, in that the items uere not identified in reviewed Qd Program documented in the FSAR.
the Reactor Licensing priate courw ot' action would have been to identifj-It appears that a more appro-by RL there eafety-related items which were not covered adeq for appropriate review FS AR o r TS.
We note that the fuel oil deficiencs ua tel-/ in the
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If you require additional information or wish to discuss this = tt
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hi further, pleas contact me.
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F. J. Nolan, Senior Reactor
,(j Inspection Specialist Light Uater Reactor Programs b ' '1 V. )
Branch, IE
-,,..-w H. D. T.wraburg, IE cc:
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