IR 05000445/1987008
| ML20236E560 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/22/1987 |
| From: | Kelley D, Will Smith, Warnick R NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20236E556 | List: |
| References | |
| 50-445-87-08, 50-445-87-8, NUDOCS 8708030008 | |
| Download: ML20236E560 (7) | |
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i U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF SPECIAL PROJECTS
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i NRC Inspection Report:
50-445/87-08 Permit: CPPR-126
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Docket: 50-445 Category: A2 Construction. Permit Expiration Date:
August 1, 1988 l
Applicant:
TU Electric j
Skyway Tower
- r4-400 North Olive Street f
Lock Box 81 l
Dallas, Texas 75201 Facility Name:
Comanche Peak Steam Electric Station (CPSES),
Unit 1
Inspection At:
Comanche Peak Site, Glen Rose, Texas Inspection Conducted:
May 1 through July 7, 1987 Inspectors:
l?FO) &
k D. L. Kelley, Senior Resident Reactor Date
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- i-Inspector, Operations (paragraphs 1, 3, 4, 5, and 6)
I?Fla hr W.
F. Smith, Resident Reactor Inspector Date (paragraphs 1, 2, 3, 4, and 5)
i Reviewed by:
9F k)M 7-EE-P7 R. F. Warnick, Assistant Director for Date Inspection Programs, Comanche Peak Project Division
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Inspection Summary Inspection Conducted: May 1 throuch July 7, 1987 (Report No. 50-445/87-08?
Areas Inspected:
Routine, unannounced safety inspection of applicant actions on previous inspection findings, class 1E 6.9 KV switchgear rework, service Water Intake cathodic protection, plant tours, and an Enforcement Conference.
Results:
Within the areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted
- R. P. Baker, Regulatory Compliance, Manager, TU Electric (TUE)
- J. L. Barker, Engineering Assurance Manager, TUE
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- R. E. Camp, Unit 1 Project Manager, TUE
- W. G. Counsil,-Executive Vice President, TUE
- R. D. Delano, Licensing Engineer, TUE
- D. E. Deviney, Manager Operations QA, TUE
- T.
L. Heatherly,. Regulatory Compliance Engineer, TUE
- J. J. Kelley, Director of Construction, TUE
- J.~E. Krechting, Director of Engineering, TUE
- J. W. Muffett,' Executive Assistant, TUE
- L. D. Nace, Vice. President, Engineering and Construction, TUE
- S.
F. Sawa, U2 Assistant Project Manager, TUE
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C. E. Scott, Startup Manager, TUE
- J.
C. Smith, Plant Operations Staff, TUE
- J. E.. Wren, QC Services Supervisor, TUE The NRC' inspectors also interviewed other applicant employees during this inspection period.
An exit interview was held with the applicant on July 7, 1987.
- Denotes personnel present at the exit interview.
2.
Applicant Action on Previous Inspection Findings (92701)
(closed) Open Item (445/8601-0-08):
Followup on the applicant's response to a question on 125 VDC Safeguards Station Battery surveillance requirements.
While conducting.a maintenance program inspection, the inspector noted that surveillance test procedure EMP-710, " Battery Performance Discharge Test" did not appear to address Technical Specification (TS) requirements for
" operability" as it applies to the performance discharge test.
The applicant subsequently explained to the inspector's satisfaction that the acceptance criteria specified in EMP-710, which is at least 80 percent of.the manufacturer's rating as required by TS 4.8.2.1.e, is the requirement for " operability."
The 18-month test frequency required by TS 4.8.2.1.f only applies when the
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battery is degraded or has reached 85 percent of its source life, but the acceptance criterion for operability remains at 80 percent of the manufacturer's rating.
The applicant's representative presented a proposed revision to EMP-710 which provided a note under the acceptance criteria to notify maintenance engineering when the service life reaches 85 percent or degradation occurs as delineated in TS 4.8.2.1.f.
This will facilitate increasing the frequency from the 60 months specified in TS 4.8.2.1.e to the 18 months required by TS 4.8.2.1.f.
The added reminder should preclude future questions and will help ensure compliance to the TS
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in this area.
No further followup is required.
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Class 1E 6.9 KV Switchaear Rework (92701)
l During the rework of the class lE 6.9 KV switchgear, the NRC
' inspector reviewed DCA 3120, Revision 1, February 29, 1979, and DCA 31447, Revision 3, April 7, 1987, to ascertain if proper engineering consideration had been given to seismic testing alteration.due to the proposed work performed during disposition of the DCA's.
The first DCA, DC 3120,.contains a Revision (Rev. 1) that calls for installation of shims between the bottom of the switchgear and the floor imbeds to bring the switchgear into a level horizontal plane.
The result of the shim additions was' excessive gap between'the switchgear floor and the concrete floor.
This in turn caused an unaccounted for, and untested seismic condition to exist.- DCA 3120 does not contain an engineering or vendor seismic evaluation study except on the weld strength of the imbed welds.
A' violation was documented in Inspection Report 445/8707, 446/8706 for untimely reporting of the switchgear floor deficiency.
DCA 31437 was written and is being dispositioned to correct the seismic problem caused by DCA 3120.
DCA 31437 calls for shims to be mounted between cubicals to reduce the intercubical distance to 1/16" or less prior to boltup.
Since the shims were not used during the original fitup or seismic testing the NRC inspector questioned whether or not the effect of the shims on seismic response was considered.
Documentation supplied by the applicant indicated that the intercubical gap reduction was directed by the switchgear vender and the DCA was concurred with by the vender as evidenced by a vender representative signature on the DCA.
No additional violations or deviations were identified.
4.
Inspection Dive of Service Water Intake Structure (92704)
The NRC inspectors attended an applicant meeting on May 18, 1987,
concerning the results of an inspection dive to examine.the cathodic protection of the service water intake structure.
Slides taken by the divers showed the deteriorating condition of the cathodic protection system and considerable algae growth.
A discussion was held to determine how the repair and modification work was to be accomplished.
A safety concern had been voiced about working in the intake structure with the service water pumps running.
A diving company representative discussed the safety precautions that would be followed if a decision was made to work with the pumps running.
His recommendations were to only have the pump furthest from the diver running and a strong cage around the pump section.
Additionally, the diver would have an anchored-safety line at the furthest point from the running pump.
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i Several other alternatives were discussed such as stopping all pumps when divers are in the water and draining the service water
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intake structure.
As of the end of this reporting period no decision had been reached on the course of action (draining versus diving).
5.
Plant Tours (71302)
The NRC inspectors performed frequent tours of Unit 1 and coenmn plant areas during this inspection period.
In addition to the general housekeeping activities and general cleanliness of the facility, specific attention was given to areas where safety-related equipment was installed and where activities were in progress involving safety-related equipment.
These areas were inspected to ensure that:
Work in progress was being accomplished using approved
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procedures.
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Special precautions for protection of equipment were
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implemented and additional cleanliness requirements were being j
adhered to for maintenance and welding activities.
Installed safety-related equipment and components were being
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protected and maintained to prevent damage or deterioration.
No violations or deviations were identified.
6.
Enforcement Conference (30702)
On July 6, 1987,.C. I. Grimes, R. F. Warnick, and D. L. Kelley met
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with W. G. Counsil, L. D. Nace, J. W. Beck, and other TU Electric staff in an enforcement conference.
J. A. Axelrad and H. E. Schierling of the Office of Special Projects in Bethesda, MD, participated by telephone, in the meeting.
The purpose of.the r.eeting was to discuss the apparent violations identified in Inspection Report 50-445/8707; 50-446/8706 regarding the failure to submit a timely report per 10 CFR 50.55(e) and the completeness of j
the nonconformance (NCR) reporting procedure.
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i During the meeting the applicant indicated that they had submitted a 10 CFR 50.55(e) report without encouragement from the NRC, even though it was not timely; however, the report was submitted one day
after senior management became aware of the facts.
The applicant indicated the lack of timeliness of the report had no adverse impact on safety of operations; therefore, the violation should be considered a Severity Level IV violation, at most.
Regarding the second apparent violation (item 445/8707-V-02) the l
applicant indicated this should not be considered a violation
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because the site procedures were intended to permit documenting
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nonconforming conditions on maintenance work requests / orders or on i
nonconformance reports.
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'The NRC indicated the information presented in the enforcement conference would be considered in the evaluation of the facts and that the utility would be informed in subsequent correspondence.
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Exit Interview (30703)
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An exit interview was conducted on July 7, 1987, with the applicant's representatives identified in paragraph 1 of this report.
During this interview, the NRC inspectors summarized the
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scope of the inspection.
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