ML20102B399
| ML20102B399 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Crystal River |
| Issue date: | 08/23/1983 |
| From: | Scinto J NRC |
| To: | Hernon R NRC |
| Shared Package | |
| ML20102A920 | List:
|
| References | |
| FOIA-84-166 TAC-49356, NUDOCS 8502090226 | |
| Download: ML20102B399 (2) | |
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August 23, 1983 4
Note to R. Hernon-
SUBJECT:
CRYSTAL RIVER - MANUAL TESTING FREQUENCY (0 ELD # 836 449)
The description of the amendment in the first paragraph of the SER and the description of the amendment to be put in the monthly notice should sound a little like the notice of proposed action published in connection with this amendment on July 25. I am attaching a xeroxed copy of the page from the Federal Register. Please have the description of the amend-
- ment in the as-issued package look somewhat closer to the description of the amendment as it was put out in the as-proposed package on July 25.
If you and Mr. Karinan can agree by phone on the language of the change,
~ the package does not need to come back to ELD. However, immediately before the amendment _is issued, check to see whether any petitions or
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comments were received. If so, come back to ELD before the amendment is issued. Do not issue before August 24, 1983.
Joe Scinto Attachment cc w/ attachment:
M. Karman
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,j33782 Fed;r:1 Regist:r / WI. 48, N,.143 / M:nd;y. July 25, 1983 / N:tices' of this policy guidance t2 dilute th) facility) loc:tedin Citrus County, frequIncy cf certain chann;l functional engineering and accidint cssessment Florida.
expertise on shift, but only to he proposed amendment would.
tests involving manual and automatic incorporate these quahfications in a change the Crystal River Unit 3 actuation oflogic circuits of the member of the operating crew. In Technical Specifications to increase the engineered safeguards Including high
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I addition, total shift manning will need to time interval between certain functional pressure injection. low pressure injection, reactor building cooling and I
be sufficient to provide staffing to tests of engineered safeguards logic' reactor building isolation. Although the handle emergency preparedness as circuits on an interim basis until I
discussed in Supplement 1 to NUREC.
appropriate control circuit modifications individualinitiation signals, the system actuation circuit design allows testing of I
0737 (December 1982), Requirements can be made at Crystal River Unit 3.
design does not permit on line testing ha t
for Emergency Response Capability" Specifically, the frequency of the
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(Generic fatter 82-33).
channel functional test of the manual many cases without actuating the Licensees may apply for modification actuation portion of the engineered system and imposing potential adverse to their Technical Specifications or safeguards system would be changed consequences on the reactor systems.,
Safety Analysis Reports to e!!minate the from monthly to once each 18 months Consideration of this amendment STA position. if they commit to during plant shutdown. In addition, the request required an assessment of the providing a required Senior Operator on scope of channel functional testing of potential adverse effects of performing shift with the qualifications described in several automatic actuationlogic these tests on a less frequent basis as Alternative 2 above. Acceptance of such circuits would be revised to prevent compared to performing the testing as modifications will be subject to NRC undesirable operation of certain currently specified. ne revised test finding that the proposal meets the components during plant power frequencies approved by this intent of this policy statement. Special operadon. Alternate tests of these amendment are based on the provis!ons attention will be given to multi-unit sites circuits wouId be specified which would for testing permitted by Section D.4 of with common control rooms and dual accomplish the intended purpose of the Regulatory Culde 1.22 where actuated licensed senior operators with regard to testing but would result in eliminating equipment is not tested during reactor the total number oflicensed staff.
undesirable consequences of performing operation and will be consistent with Invitation To Comment the testing. De request for this char.ge test frequencles included in Standard was made by the licensees
- application Technical Specifications. Specifically.
Commissioner Roberts would like to
,f r amendment dated January 14.1983, Position D.4 of Regulatory Guide 1.22 receive public comments on the nad for and 8upplemented on January 20,1983, excludes the requirement to test some form of **or equivalent" provision July 8.1983 and July 14,1983.
actuated equlpment during reactor in the Policy Statement and the Before issuance of the proposed operation where such action could adversely affect safet or operability of dards to be met in establishing
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D te Washington.DC, on this 19th day the t n el
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l a r m$nission has made a proposed pejec av(d or the Nuclear Regulatory Commission.
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Samuet }. Qilk, determination that the amendment c
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5 Secretoryofthe Comm/ss/on.
request involves no significant hazar' s on failure of these es from tests that d
p mewg-,
, consideration. Under the Commission a had been conducte ince the plant '
i h s means went into commercial opera tion In early oe ion of fac I yin 1977. Based on a review of the testing
- accorkance with the p! posed and maintenance history of these ro hdmN reaseinth prob lk I
systems, no failures were Identified to ea 111 y or have occurred in the logic matrix relay Florida Fower Corp., et at; consequences of an accident previously hnt n fud)s d
8 Consideration of Issuance of evaluated; or (2) create the possibility of f
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In f Amendment to Facility Operating a new or different kind of accident from Section D.4 of Regulatory Culde 1.22 are Ucense and Proposed flo Significant any accident previously evaluated; or (3) met with the licensees proposed interim Hazards Cons!deration Determination involve a significant te uction in a surveillance test pr am.The staff has and Opportun!!y for Hearing 8
ma n of s '
required testing of al channels in the ne U.S. Nuclear Regu!atory (c,u ls 'on has provided automa tic logic circuits by the licensee Commission (the Commission is ruldance concerning the application of befm restart from me curnnt ufue!Ing considering issuance of an am)endment these standards by providing certain-outage.
to Facility Operating 1.icense No. DPR-examples (48 FR 14870). One of the Interim re!!ef for testing of these items 72, issued to Florida Power Corporation.
examples ofguidance regarding detions was given in I.fcense Amendment No. et
. City of Afachua, City of Bushnell, City of not likely to involve significant hazards dated January 24,1983 for the period considerations is a change which either January 24,1983 through the end of Fuel -
g Cainsville, City of Kissimme. City of may result in some increase to the Cycle 4 (March 1983). The licensees Leesburg. City of New Smyrna Beach probability or consequences of a have committed to a long. range program q
and Utilities Commission, City of New previous'y analyzed accident or may
'to install circuit modifications where s
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. Smyma Beach. City of Ocala, Orlando reduce in some way a safety margin, but possible, to enable complete testin Utilities Commission and City of.
Orlando, Sebring Utilities Commission, where the reulis of the changs are during power operation.Herefore,gthe,
clearly within all acceptable criteria Commission propose (lo determine that Seminole Electric Coopera t!ve, Inc., and.with respect to the spem or component. the amendment willinvolve no the City of Ta!!ahassee (the licensees). -
specified in the Standard Revfew Plan, significant hazards considerations. -
for operation of the Crystal River Unit In this case, the !! censers have,
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He Conimission is seeking public -
No. 3 Nuclear Generating plant (the requested approval to change the -
comments on this proposed, e
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