ML20035B724
| ML20035B724 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/29/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20035B722 | List: |
| References | |
| 50-373-93-07, 50-373-93-7, 50-374-93-07, 50-374-93-7, NUDOCS 9304050038 | |
| Download: ML20035B724 (2) | |
Text
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Docket Hos. 50-373; 50-374
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Commonwealth Edison Company License Nos. NPF-11; NPF-18 laSalle County Station, Units 1 and 2 During an NRC inspection coriducted on February 8 through March 15, 1993, i
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 (1993), the violations are listed below:
l 1.
Technical specification 6.2.B requires radiation control procedures to-l be maintained and adhered to.
LaSalle Radiation Procedure (LRP) 1350-20, "The Startup and Operation of the Single Channel Cuntinuous Air Monitor (CAM)," Revision 6, step F.4, j
requires performance of a daily routine on the single channel CAMS l
including a source check and other operational checks and step E.1 l
t requires notification of health physics supervision if equipment does not function properly.
LRP 1350-24, "Startup and Operation of the Manifold Sample System Continuous Air Monitors," Revision 7, step E.2, requires notification of i
health physics supervision if the equipment does not function properly.
Contrary to the above, the daily routine was not performed on one or both single channel CAMS OPLAlJ and OPLBlJ for the refueling floor on 1, 4, 5, 8, 16-18 and February 1-5, 1993. Health physics January supervision was not informed that equipment did not function properly l'
upon daily source check failures of manifold sample system CAMS IPL83JA a
(on January 31 and February 1, 3-5, 1993) and IPL15J (on February 1-6, 1993) for the Unit I reactor building and primary containment and upon daily identification on January 19-22, 1993 that single channel CAM OPLB1J for the refueling floor was shutdown.
This is a Severity Level IV violation (Supplement 1).
Technical specification 6.2. A.a requires written procedures recommended 2.
in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, be established, implemented, and maintained.
Regulatory Guide 1.33 includes administrative procedures and procedures for performing maintenance and surveillances.
LaSalle Maintenance Procedure (LMP)-MS-06, " Removal / Installation of Main Steam Safety Relief Valves," step.F.7.26.8, requires tape to be removed from the actuator air valve exhaust port at the bottom of the cylinder i
l head.
LaSalle Administrative Procedure (LAP)-300-7, "Pr paration and Control t
i of Huclear k'ork Request," Appendix C, step C.31, requires maintenance to be performed as required by the work instructions ar.d step C.60 requires.
i performance of identified post maintenance testing.
9304050038 930329^
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LaSalle Technical ~ Surveillance (LTS)-1100-6, " Local Power Range Monitor (LPRM) Cable Connection Verification", step T.I.C, requires verification that LPRMs are properly connected.
Contrary to the above, administrative procedures and procedures for performing maintenance and surveillances were not correctly implemented in the following examples:
In December 1992, tape was not removed from the actuator air valve a.
exhaust port at the bottom of the cylinder head for Unit I safety rdief valve 'A' in accordance with LMP-MS-06.
i b.
Work was not performed as specified in the work instructions for work request (WR) Ll7076 in late 1992 and WR L21004 on February 16, 1993, in accordance with LAP-300-7 as Unit 1 LPRM 32-41 was connected incorrectly.
j On December 2, 1992, Unit 1 LPRM 32-41 was not verified as being c.
properly cor.nected in accordance with LTS-1100-6.
d.
On February 16, 1993, post maintenance testing to verify proper connection of LPRM 32-41 identified in WR L21004 was not performed in accordance with LAP-300-7.
I I
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Commonwealth Edis'en is hereby required to submit a written statement or explanation to the U.S. Nuclear-
~
f Regulatory Commission, ATTN: Document Control Desk, Washington D.C. 20555, with a copy to the U.S. Nuclear Regulatory Commission, Region 111, 799 Roosevelt Road, Glen Ellyn, Illinois, 60137, and a copy to the NRC Resident Inspector at the LaSalle County. Station within 30 days of the date 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 l
each violation:
(1) the reason for the violation or, if contested, the basis l
for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will bc taken to avoid i
further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order or a demand for information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
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Dated at Glen Ellyn, Illinois l
this 2/d(day ofWesil993
[~ Brent Clayton, Chief.
l Reactor Projects Branch 1 l
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