IR 05000277/1979001
| ML19282C576 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/16/1979 |
| From: | Greenman E, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19282C578 | List: |
| References | |
| 50-277-79-01, 50-277-79-1, 50-278-79-01, 50-278-79-1, NUDOCS 7903300352 | |
| Download: ML19282C576 (4) | |
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I U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT C0-277/79-01 Report No. 50-278/79-01 50-277 Docket No.50-77R DPR-44 C
License No. DPR-56 Priority Category C
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Licensee:
Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Facility Name:
Peach Bottom Atomic Power Station Units 2 and 3 Inspection at:
Delta, Pennsylvania Inspection conducted:
January 2-5, 1979
. Inspectors:
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E. G. Greendlafi, Rdactor Inspector date signed date signed date signed Approved by:
8.C. d b % h.
Q.I16l71 E. C. McCabe, Jr., Chief, Reactor Projects, date signed Section No. 2, RO&NS Branch Inspection Summary:
Inspection on January 2-5,1979 (Combined Report Nos. 50-277/79-01 and 50-278/79-01)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of nonroutine event review (in-office and on site review), review of periodic reports, plant operations, facility tours and independent effort.
The inspection involved 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> on site at Unit 2 and 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> on site at Unit 3 by one NRC regional based inspector.
Results: No items of noncompliance were identified.
7903300362.
Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted J. Davenport, I&E Engineer R. S. Fleischmann, Assistant Station Superintendent
- W. T. Ullrich, Station Superintendent J. Winzenried, Technical Engineer Other licensee employees were contacted during the inspection. These included engineering personnel, reactor operators, technical support, health physics and security personnel.
- denotes presence at exit interview.
2.
Facility Tours Facility tours were conducted on an unescorted basis of Unit 2 and Unit 3.
Areas examined included security access controls, verification of minimum control room staffing and general plant status.
Inspections were conducted to determine the general state of cleanliness, fire watch status (cable spreading room) and to observe housekeeping and plant conditions.
The inspector checked equipment operability and verified by comparison of selected control room instrumentation that limiting conditions for operation were being satisfied.
Selected locked valves were checked and found to be locked as required.
Status of High Radiation Area locked doors (sampling) was verified.
The Shift Supervisors Log cnd Unit 2 and Unit 3 Operators Log for the interval January 2-4, 1979 was also reviewed.
No unacceptable conditions were identified.
3.
Modifications (Electrical) for Peach Bottom 2 Combined Inspection Reports 50-277/78-28 and 50-278/78-31 Detail 3 reference replacement of A.P.I splices on relief ~ valves and MOVs. The inspector noted that the licensee's program involved re-inforcement of these splices with WCSF-N splice material over the existing API material.
The inspector had no further question regarding this item as related to Unit 2.
The inspector also reviewed a licensee letter A. Sellers to S. L. Daltroff, dated January 2, ~1979 concerning this subjec.
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4.
'Non-Routine Event Review The inspector reviewed the following non-routine events both in-office and onsite for safety significance, circumstances, and relationship to Technical Specification protective limits.
The licensee's review, evaluation and corrective action was also verified.
LER Number 2-78-48-3L-0
"A" channel main steam line high flow circuitry in primary containment isolation signal logic used for Group I isolation failure due to contact pair return spring out of adjustment.
2-79-1/lP A review of safeguard cable routing identified eight cables which were improperly designated as non-safeguard cables.
The inspector also visually confirmed that a fire-watch had been stationed in the cable spreading room area and monitored work in progress for rerouting at Unit 2.
The licensee's review to determine that no additional problems of this type existed was approximately 90 percent complete at the conclusion of this inspection.
Results of this review will be examined during a subsequent inspection.
(50-277/79-01 and 50-278/79-01)
3-78-22/3L-0 RHR Motor Operated Valve (M01548) failed to reopen during surveillance due to a loose drive sleeve lock nut backing off.
5.
In-office Review of Periodic and Special Reports The following licensee re' orts have been reviewed in-office:
a.
Annual Operating Report No. 2 (Peach Bottom) January 1, through December 31, 1977 b.
Semi-Annual Effluent Release Report (Peach Bottom) January -
June,1978
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The referenced reports were reviewed pursuant to Technical Specifications to ascertain if all required information was contained therein.
Onsite followup of specifications is documented in IE Combined Inspection Report 50-277/79-02 and 50-278/79-02.
6.
Exit Interview Meetings were held periodically during the course of this inspection with plant management and at the conclusion of the inspection as identified in Detail 1.
The licensee acknowledged inspection findings.
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