ML20235L867
| ML20235L867 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 07/13/1987 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20235L858 | List: |
| References | |
| 50-295-86-32, 50-304-86-32, NUDOCS 8707160856 | |
| Download: ML20235L867 (2) | |
Text
___
g NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-295 Docket No. 50-304 As a result of the inspection conducted on December 10 through January 16,
.1987, and in accordance with 10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for NRC Enforcement Actions (1985), the following violations were identified:
1.-
Technical Specification 3.9.5 requires that containment integrity shall not be violated when a nuclear core is installed in the reactor unless the reactor is at cold shutdown and the shutdown margin is greater than 1% delta k/k.
Technical Specification 3.0.3 states that if Limiting Conditions for Operation cannot be met, actions shall be taken within one hour to place-the reactor in hot shutdown within the following four hours.
Contrary to the above, from January 20, 1986 through November 30, 1986, with the reactor above cold shutdown, Unit 2 containment integrity was violated and action was not taken to place the unit in hot shutdown.
Containment integrity was violated because valves 20W0030 and 20W0038 were open.
This is a Severity Level IV violation.
(Supplement I) (304/86032-01(DRP))
2.
10 CFR 50 Appendix B, Criterion III, as implemented by Commonwealth Edison Company Topical Report (CE-1A), Section 3, requires that measures shall be established to assure that applicable regulatory requirements and the design basis for systems to which Appendix B applies are correctly translated into specification and procedures.
Contrary to the above, the licensee failed to establish measures sufficient to ensure that valves DW0030 and DW0038, which were identified in both the FSAR and the design drawings as containment isolation valves, were correctly translated into the containment isolation valve list in Table 4.9-3 of the facility Technical Specifications, and into station operating procedures.
This is a Severity Level IV violation.
(Supplements)
(295/86032-01(DRP); 304/86032-02(DRP))
Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation:
(1) corrective action
)
Q7160856870713 G
DOCK c5000295 PDR l
l
JUL } $ 1987 taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
JUL 131987
.ga <m A Dated Charles E. Norelius, Director Division of Reactor Projects J