ML20126K623
| ML20126K623 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/12/1985 |
| From: | Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20126K615 | List: |
| References | |
| 50-440-85-17, NUDOCS 8506190297 | |
| Download: ML20126K623 (2) | |
See also: IR 05000323/2005010
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Appendix
The Cleveland Electric Illuminating
Docket No. 50-440
Company (CEI)
As a result of the inspection conducted on March 23 through May 10, 1985, and
in accordance with the General Policy and Procedures for NRC Enforcement
Actions, (10 CFR Part 2, Appendix C), the following violations were identified:
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1.
10 CFR 50, Appendix B, Criterion V, as implemented by CEI's Corporate
Nuclear Quality Assurance Program (CNQAP), Section 0500, Revision 6,
states that " activities affecting quality shall be prescribed by documented
instructions, procedures, or drawings, of a type appropriate to the
circumstances and shall be accomplished in accordance with these
instructions, procedures, or drawings".
Contrary to the above, sufficient administrative controls were not
prescribed in appropriate procedures to adequately govern conduct of
integrated run-in testing activities performed under control of Temporary
Operating Instructions prior to preoperational test release for
performance (440/85017-01(DRS)).
This is a Severity Level IV violation (Supplement II).
2.
10 CFR 50, Appendix B, Criterion V, as implemented by CEI's CNQAP,
Section 0500, Revision 6, requires that activities affecting quality
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shall be accomplished in accordance with procedures.
Contrary to above, the Low Pressure Core Spray System, a safety related
system required for safe shutdown was operated without utilizing (or in
accordance with) procedures (440/85017-07(DRS)).
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This is a severity Level IV violation (Supplement II).
3.
10 CFR 50, Appendix B, Criterion V and Regulatory Guide 1.68, Revision 2,
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as implemented by CEI's CNQAP, Section 0500, Revision 6, requires that
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activities affecting quality shall be prescribed by documented
instructions of a type appropriate to the circumstances and that test
procedures shall include appropriate checklists and signature blocks to
control test performance and the sequence of testing.
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Contrary to the above, Perry Nuclear Fower Plant Test Program
Instruction, TPI-7 "Preoperational, Acceptance and Special Test Procedure
Preparation, Review and Approval" was not appropriate to control test
performance and the sequence of testing for test procedures as described
in Paragraph Sa (440/85017-08(DRS)).
This is c Severity Level V violation (Supplement II).
8506190297 850612
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Appendix
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4.
10 CFR 50, Appendix B, Criterion V, as implemented by CEI's CNQAP,
Section 0500, Revision 6, states that " activities affecting quality shall
be prescribed by documented instructions, procedures, or drawings, of a
type appropriate to the circumstances and shall be accomplished in
accordance with these instructions, procedures, or drawings." Test
Program Instruction-27 Section 4.2 requires that pretest checklists be
completed as part of the release for test package.
Contrary to the above, actions pursuant to these checklist verifications
were inadequately accomplished in conjunction with test procedures
TP 1E12-P001, " Residual Heat Removal (RHR) System" and TP 1R43-P001,
" Division 1 Standby Diesel Generator."
Checklist verifications conducted
to ensure that design changes are incorporated into the test procedure and
that the test procedure is written to the latest approved revision of
design documentation and to the as-built condition of the plant did not
identify the need to incorporate Engineering Change Notice NJ35313 into
the RHR test procedure. This design change had already been depicted on
plant drawings and in the as-built plant condition.
In addition, checklist
verifications conducted to ensure that lifted leads and jumpers had been
reviewed for impact on standby diesel generator testing did not identify
a jumper installed which bypassed the diesel generator out-of-service
alarm (440/85017-05(DRS)).
This is Severity Level V violation (Supplement II).
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 item of noncompliance:
(1) cor-
rective action taken and the results achieved; (2) corrective action to be
taken to avoid further noncompliance; and (3) the date when full compliance
will be achieved. Consideration may be given to extending your response time
for good cause shown.
JUN 121985
h%hye ,
Dated
R.
L'. Spessard, Director,
Division of Reactor Safety
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