ML16341F653
| ML16341F653 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/02/1990 |
| From: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16341F654 | List: |
| References | |
| 50-275-90-01, 50-275-90-1, 50-323-90-01, 50-323-90-1, NUDOCS 9004200460 | |
| Download: ML16341F653 (8) | |
Text
'i APPENDIX A NOTICE OF VIOLATION k
Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, California 94106 Diablo Canyon. Units 1 and' Docket Nos.
50-275, 50-323 License Nos.
DPR-80, DPR-82 During an NRC inspection conducted on January 3 -
12 and January 22 through February 2, 1990, violations of NRC requir'ements 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.
Section 6.8.1 of 'the Diablo Canyon Technical Specifications
- states, in part, "h'ritten procedures shall be established, implemented and maintained covering the activities referenced below:
a.
'The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978."
Regulatory Guide 1.33, Revision 2, Appendix A, Section 8.b, states that
"... procedures are required for each surveillance test, inspection...
listed in the technical specifications."
Section 6.8.3 of the Technical Specifications states:
"Temporary changes to procedures'f Specification 6.8. 1 above may be made provided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit affected; and c.
The change is documented, reviewed and approved by the Plant
- Manager, or by a technically qualified manager who reports directly to the Plant Manager as previously designated by the Plant Manager, within 14 days of implementation."
Licensee Administrative Procedure, AP E-484, Issuance and Approval of On-The-Spot Changes to Procedures, Revision 15, Section 2.1, states, in part:
"It is necessary to issue an On-The-Spot Change (OTSC) if...
The procedure cannot be followed as written."
9004200460 9'00402 PDR ADOCK 05000275 6
PNU
~
Contrary 'to %he above:
1.
On November 14, 1989, during performance of surveillance procedure STP.V-4A, "Functional Test of ECCS Check Valves,"
Revision 3, a procedure step was added following step 8.3.1 directing the operator to "close
- 112B, 112C."
In addition, a notation was added at step 8.2.26 to specify recording the sum of 'flow indicators FI-9718 and TI-970B instead of'ecnrdinq the indicated flow on FI-9718 only, as specified in the pro-cedure.
Proper approval of these temporary changes was not
.provided by the issuance of an OTSC.
2.
On December 1, 1989, during performance of surveillance pro-cedure STP.V-5A, "ECCS Check Valve Leak Test, Post-Refueling Maintenance,"
Revision 5, Step 7.5 was changed to not require verification of current calibration of safety injection test line flow instruments FI-928A and FI-928B, and proper approval of this temporary change was not provided by the issuance of an OTSC.
3.
On December 4,
1989, during performance of surveillance procedure STP.V-SC, "ECCS Hot Leg Check Valve Test,"
Revision 2, Step 7.4 was changed to not require verification of current calibration of safety injection test line flow instruments FI-928A and FI-928B, and proper approval of this temporary change was not provided by the issuance of an OTSC.
4.
On December 4, 1989, during performance of surveillance pro-cedure STP.V-5C, "ECCS Hot Leg Check Valve Test", Revision 2, Step 8.16.25 was changed to specify capping of valve SI-41, and proper approval of this temporary change was not provided by the issuance of an OTSC.
This is a Severity Level IV violation, applicable to Unit 1.(Supple-ment I).
B.
- 10CFR50, Appendix B, Criterion XVI, Corrective Action, requires that measures be established to assure that conditions adverse to quality are promptly identified and corrected.
Contrary to the above, a condition identified on action request (AR)
A0021200, dated April 1, 1986, had not been corrected as of February 2, 1990.
This condition involved potential loss of flow for the steam generator blowdown tank vent system gross radioactivity monitor (RM-27),
such that it could become inoperable without warning.
This is a Severity Level IV violation, applicable to Units 1 and 2
(Supplement I).
0 C.
10 CFR'Part '50, Appendix B, Criterion V states, in part:
"Activities affecting quality shall be prescribed by documented instructions...
and shall be accomplished in accordance with these instructions....."
The licensee's approved procedure NPAP C-10, Revision 10, "Nuclear Plant Administrative Procedure, Housekeeping - General," states, in part, "Plant areas and equipment should be cleaned on a regular basis,,con-sistent with their accessibility during operation, and their required cleanliness level."
Appendix 6. 1, Minimum Housekeeping Requirements, states in part that "Combustible materials,*such as oil-soaked and paint-covered
- rags, waste,
- shaving, packing and rubbish shall not be allowed to accumulate on benches, floors, or yards....
Stairways, aisles, exits,... shall be kept reasonably clear and free from obstruc-tions, depressions and debris.". 1 to NPAP C-10, "Fire and Industrial Safety Housekeeping Survey Checklist," states in items 11.4 and 12.2, "Cable tray fire stops are in good condition," and "Electrical panels are free of accumulated dust."
The licensee's approved procedure APC-10S3 "Administrative Procedure, Revision 1, Plant Housekeepina Areas," states in part:
"4.6 As a general rule, the minimum acceptable standard for an area is as follows.
"4.6.1 All floor areas have been swept and are clear of debris.
"4.6.2 Any uncontained oil in the area has been wiped-up and or cleaned from pipes, pump bases, etc.
"4.6.3 Materials are stored only in designated areas.
For example,
- hoses, ladders, chairs, stools, carts, panels, etc.,
are returned to their designated storage or otherwise secured.
"4.6.4
Response
and resolution to housekeeping discrepancies or concerns raised in his area during NPG management inspec-tions are Addressed in a timely manner."
Contrary to the above, during an inspection conducted on January 8 -
12 and January 22 - February 2, 1990, the following conditions were observed:
Damaged cable tray'fire barrier in Unit 2 4KV vital cable spreading room (on north wall, separating rooms "G" and "H").
A piece of.fire stop material 6" x 2" x 1" was missing on the H side of the fire stop.
Debris in the bottom of panel 1PM247 (by Unit 1 oil-water separator
- room, 85 foot level)
Cigarette butts in components located in the following no-smoking areas:
(1) in a fire stop separating Unit 2 4KV vital cable spreading rooms "G" and "H", on the "G" side of the fire stop, and (2) in safety panel
- RNPIC, Rack No. 3, Unit 2 cable spreading room.
0
4" Masking tape and cardboard tag in Unit 2 remote shutdown panel White plastic bottles and.debris.on floor at 85-foot level,.Unit 2
containment penetration area Black duct tape and miscellaneous debris (bolts/nuts) on floor at 100-foot level, Unit 1 near auxiliary feedwater (AFW) valves, north side of containment Tools, parts, and other debris in instrument cabinets Panels 1-PM-82, 2-PM-72, air compressor control panel PM-150 (also had broken handle)
Oil and grease under air compressors 5 and 6
Portable vent fan, air sampler, and extension cords (not is use) near AFW valves on 100 foot level, Unit 1
Cardboard cartons, etc., stored on top of computer, Unit 1 Plant Computer Room This is a Severity Level IV violation, applicable to Units 1 and 2
(Supplement I).
Pursuant to the provisions of 10 CFR 2.201, the Pacific Gas and Electric Company is hereby required to submit a written statement or explanation to the U. S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator, Region V,
and a copy to the NRC Senior Resident Inspector, Diablo Canyon Power Plant, within 30 days of the date of the letter transmitting this notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, if
- admitted, (2) the corrective steps that have been taken and the results
- achieved, (3) the corrective steps that will be taken to avoid 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 may be issued to show cause why the license should not be modified, suspended, or revoked or'why such other action as may be proper should not be taken.
Consideration may be given to extending the response time for good cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION Dated this day of March, 1990 at Walnut Creek,,California Jo n B. Marts n Regional Administrator