ML17083C482
| ML17083C482 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 05/13/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16342A114 | List: |
| References | |
| 50-275-93-11, 50-323-93-11, NUDOCS 9306010226 | |
| Download: ML17083C482 (4) | |
Text
NOTICE OF VIOLATION Pacific Gas and Electric Company Diablo Canyon Power Plant San Francisco, California Dockets 50-275 and 50-323 Licenses DPR-80 and DPR-82 EA.93-107 During an NRC inspection conducted on April 5 28, 1993, violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C, the violations are listed below:
A.
TS 6.8.4 requires in part that the licensee establish, imp'lement, and maintain a program which will ensure the capability to obtain and analyze-reactor coolant samples and samples of radioiodines and particulates in plant gaseous effluents under accident conditions.
The program must.
include the following:
(1) training of personnel, (2) procedures for sampling and analysis, and (3) provi sions for mai ntenance of sampling and analysis equipment.
Contrary to the above:
1.
During the periods of August 24 October 15,
- 1992, November 6 December 10,
- 1992, December 31, 1992 February 12,
- 1993, and February 25, 1993 April 6,
- 1993, the licensee failed to implement and maintain a program in Unit 2 which ensured the capability to obtain and analyze reactor coolant samples under accident conditions, in that:
(a) the principal means of quanti fying reactor coolant dissolved hy'drogen, using an in-line exosensor, was inoperable during these periods; (b) the licensee had discontinued training, procedures, and calibration for quanti fying reactor coolant dissolved hydrogen with the SENTRY gas chromatograph; and (c) the licensee 's remaining alternate methods of quanti fying reactor coolant dissolved hydrogen (i.e., liquid grab samples analyzed by normal laboratory methods) could not be used, under accident conditions resulting from a major loss of coolant accident with core
- damage, without exposing individuals to a
prohibitive dose.
2.
As of harch 9,
- 1993, the licensee had failed to implement a program which ensured the capability to obtain and analyze samples of radioiodines and particulates in plant gaseous effluents under accident conditions, in that:
(1) the licensee's program relic'rimarily on P,=-32, a moni tor which could not have obtained the required samples under certain -ccident condi:ions (i.e.,
a loss
=;:.
st, coolant accident with major cove d=-mage),
and (2) for Ri,-~.G, li.e only sampl="l capable cf obtaini".o
'L.he veouived sc,maples und=v c;".'.".:
vie
<<It
~as>s I'
Io I s tv ilc II '
s cs
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Pyg(nftgtg&
provisions to ensure that the monitor would not be left out of service for excessive periods.
This is a Severity Level IV violation (Supplement I).
B.
10 CFR 50.59 requires in part that the licensee maintain records of changes to the facility or procedures described in the Updated Final Safety Analysis Report
{UFSAR), including a written safety evaluation that provides the basis for determining that the change does not involve an unrevi ewed safety questi on.
The UFSAR for Units 1 and 2, Section 9.3.2.2, "Post-LOCA. Sampling ccident conditions t
" d
'b s the licensee's facilities and procedures for obtaining prompt remote samples of reactor coolant under acci en including the system capability for "quantifying reactor coolant disso ve hydrogen using the chemical analysis panel.
Contrary to the above, as of April 9,
- 1993, the 'licensee had not maintained records of a change to the facility as described ln UlFSbARt Section 9.3.2.2, in that, on August )8,
- 1992, procedures and ca i ra ion were discontinued for quantifying reactor coolant dissolved hydrogen at the chemical analysis
- panel, and no written safety evaluation of this change was performed for either Unit 1 or 2..
This is a Severity Level IV violation {Supplement I).
P t t the provisions of 10 CFR 2.201, Pacific Gas and Electric Company is hereby required to submit a writtep statement or expla Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C.
20555
'th copy to the Regional Administrator, Region V, and a copy to the NRC Resident Inspector, Diablo Canyon Power Plant, withi y
wi a
of the letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each viol ati on:
(1) the reason for the violati on, or, if contested, the basis for disputing the violation,
{2) the corrective steps that have been tal en and the results
- achieved,
{3) the corrective steps that wi e
a en'o
'll b t k to avoid further violations, and (4) the date when full compliance will be achieved.
If'an adequate reply is noot received within the t>me speci i e in i s
'f' 'h Notice an order or a Demand for Information may be ied sus
- ended, or issue
'ued to show cause why the license should not be modifie p
not be taken.
l here good cause is shown, consideration will be given to exten re'vo e, o
k d r why such other action as may be proper should not din the res onse p
time ~
Dated ~t l!alnut Creek, California this
'."c.h day of 1993