IR 05000277/1979018
| ML19260C502 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/02/1979 |
| From: | Greenman E, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19260C499 | List: |
| References | |
| 50-277-79-18, 50-278-79-20, NUDOCS 8001070274 | |
| Download: ML19260C502 (8) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-277/79-18 Report No.
50-278/79-20 50-277 Docket No.
50-278 DPR-44 C
License No. DPR-56 Priority
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Category C
Licensee:
Philadelphia Electric Comoany 2301 Market Street Philadelphia, Pennsylvania 19101 Facility Name:
Peach Bottom Atomic Power Station Units 2 and 3 Inspection at:
Delta, Pennsylvania Inspection conducted:
July 1 - July 31, 1979 Inspectors:
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JO->-7f E. G. Greenman, Resident Reactor Inspector date signed date signed date signed 0 b ! '- GA
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A Approved by:
f E. C. McCabe, Jr., Chief, Reactor Projects date signed Section No. 2, RO&NS Branch Inspection Summary:
Inspection on July 1 - July 31, 1979 (Combined Inspection Report Nos. 50-277/79-18 c.nd 50-278/79-20)
Arcas Inspected:
Routine, onsite regular and backshift inspection by the resident inspector (44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> Unit 2; 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> Unit 3).
Areas inspected included accessible portions of the Unit 2 and Unit 3 facilities, physical security, plant operations, facility tours, control room inspections, IE Bulletin and Circular followup, LER reviews onsite and in-office, radiation protection, and review of periodic reports.
Results: No items of noncompliance were identified in eight areas and one item of noncompliance was identified in one area related to physical security barrier control - (Infraction, Detail 8).
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D1 0 S 001 R:gion I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted C. E. Andersen, Operations Engineer J. Austin, Engineer - Maintenance Division W. Barley, Health Physics
- R. S. Fleischmann, Assistant Station Superintendent S. Roberts, Results Engineer S. Tharpe, Security Supervisor
- W. T. Ullrich, Station Superintendent Other licensee employees were contacted during this inspection.
These included engineering personnel, administrative personnel, reactor operators, shift supervision, maintenance personnel, health physics personnel, and security personnel.
- denotes those present at entrance and exit interviews.
2.
Previous Inspection Item Update (Closed)
Unresolved item (79-11-01 and 79-12-01) - Valve position inconsistency between PCID (M-361, Sheets 1 and 2) and Check-Off List (S.3.2.A.1.A.2 and S.3.2.A.1.A.3) for RHR pressurizing to shutdown cooling header outer valve (Units 2 and 3).
The inspector reviewed revised check lists dated June 5, 1979 which corrected inconsistencies.
The inspector had no further questions regarding this item.
(Closed)
Infraction (79-11-02 and 79-12-02) - Failure to follow procedures in maintaining valve positions as required.
The inspector confirmed that instructions to shift personnel had been provided.
Corrective action was verified as specified in licensee's response to NRC Region I dated May 10, 1979.
The inspector had no further questions regarding this item.
(Closed) Deficiency (79-12-03) - Failure to properly review and approve a temporary procedural change for testing changes regarding Main Steam Line Drain MO-74.
The inspector confirmed that PORC signatures had been obtained by the licensee and that PORC minutes dated April 18, 1979 contained documentation of PORC review for this change.
The surveillance test was verified to now contain required signatures.
The inspector also verified that revisions to A-3 were in processing, which classify temporary procedure changes.
Corrective action was verified as described in licensee's response to NRC Region I dated May 10, 1975.
The inspector had no further questions regarding this item.
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3.
Logs and Records The following logs and records for the periods indicated were reviewed pursuant to the licensee's administrative requirements.
Management review was evidenced by frequent log book initialing.
a.
Shift Supervision Log - July 1-31, 1979 b.
Unit 2 Jumper Log - Current entries c.
Unit 3 Jumper Log - Current entries d.
Reactor Operators Log Book Unit 2 - July 1-31, 1979 e.
Reactor Operators Log Book Unit 3 - July 1-31, 1979 f.
ACO Log Book - July 1-31, 1979 g.
Round Sheets Sampling Audit h.
Night Order Book - All current entries i. Maintenance Request Forms Units 2 and 3 - Sampling Audit July, 1979 j.
Security Records 4.
Facility Tours a.
During the course of this inspectica, which also included backshifts, the inspector conducted daily tours of accessible facility areas and made observations of:
Control Room (daily)
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-- Turbine Building (all levels)
-- Reactor Building (all accessible areas)
-- Diesel Generator Building Yard area and perimeter exterior to the power block
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Security Building and Control Points including power block
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-- Maintenance Shop
-- Security Fencing
-- Lighting Radwaste
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Vehicular control
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-- Drum Shipping Areas Personnel
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b.
The following observations were made by the inspector.
The inspector frequently confirmed that selected instruments were operational and indicated values were within Technical Specification limits.
Specific examples included ECCS controller positions, flow setpoints and proper valve positioning, inerting status, suppression pool limits, PCIS status, nuclear instrumen-tation, radioactive effluent indication drywell temperatures, and diesel generator operability.
No unacceptable conditions were identified.
Valve Positions.
The inspector verified that selected
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valves in safety related systems were maintained locked as required and were properly positioned. Exterior pit locked valves were also examined.
No unacceptable conditions e e96254 identifie.
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Radiation Controls.
The inspector verified by direct obser-
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vation that access and control point procedures and posting requirements were being followed. Observations also included adherence to RWP requirements, including the correct use of protective clothing. The inspector also confirmed that high radiation areas were being maintained locked based on weekly checks of numerous locked doors.
Personnel were observed to properly curvey using " friskers", portal monitors, when exiting the power block and upon leaving the facility.
The inspector also performed sampling audits of personnel within the protected area and radiological control area to verify that proper dosimetry and badging requirements were being displayed and worn.
The inspector also confirmed that survey instrumentation calibrations were maintained current for instrumentation in use.
No unacceptable conditions were identified.
Plant Housekeeping and Fire Protection.
The inspector
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observed housekeeping conditions, fire hose station status, and extinguisher checks conducted by the license-cnd observed the licensee's fire protection procedures and practices as well as observations of plant conditions including firewatch controls.
No unacceptable conditions were identified.
-- Fluid Leaks. No significant fluid leaks were observed which had not been identified by the licensee nor for which necessary corrective action had not been initiated.
-- Piping Vibration. No significant piping vibrations or unusual conditions were observed.
Anchor plates, bolts, and seismic restraints were observed
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and no unusual conditions were noted.
Specific anchor bolt failures disclosed pursuant to IE Bulletin 79-02 have been reported by the licensee (Detail 5).
-- Annunciated Alarms.
Selected annunciators known to constitute off normal conditions were discussed with control room operators to verify that operators and shift supervision were knowledgeable of plant conditions and that corrective action, if required, was being taken.
-- Control Room Manning.
On frequent occasions during this inspection, the inspector confirmed that requirements of 10CFR50.54(k) and Technical Specifications for minimum staffing requirements were satisfied.
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5.
Non-Routine Event Review The inspector reviewed the following non-routine event onsite and in the NRC site office for safety significance, circumstances, and relationship to Technical Specification protective limits.
The licensee's PORC review, evaluation, and corrective action was also verified.
LER Number Title 2-79-33/IP Anchor Bolt Inspection Program conducted pursuant to IE Bulletin 79-02 identified a failure in one support associated with the emergency cooling water lines in the emergency cooling tower valve room.
The inspector reviewed Concrete Expansion Bolt Situation Report dated July 10, 1979.
Two 3/4 inch shell type bolts failed the required torque test and pulled out during testing.
The bolts have been replaced with one and one quarter inch Hilti Wedge type anchors.
Bolts were relocated at different locations on this support plate subsequent to engineering review. The inspector determined that the specific piping being supported would be placed in service during a flood or a loss of the Conowingo Pond.
Loss of a single piping support may not have resulted in piping failure coupled with a seismic event occurring simultaneously with flood / loss of Conowingo Pond. Based upon completion of the licensee's corrective action, the inspector concluded that the safety hazard from anchor bolt failure was minimal after repairs were completed.
6.
IE Bulletins, Circular, and Information Notice Review Incpection was p aformed for the following IE Bulletins and Circulars to verify whether:
the Bulletins and Circulars were received by licensee management; review for applicability was performed; corrective action (if any) was initiated and/or evaluated; whether responses, as required, were submitted in the necessary time frame and supporting documentation evidencing the licensee's review was contained in PORC minutes.
Findings were as follows:
IE Bulletin 78-12 " Atypical Weld Material in Reactor Pressure Vessel Welds" dated November 22, 1978.
IE Bulletin 78-12A " Atypical Weld Material in Reactor Pressure Vessel Welds" dated November 24, 1978.
IE Bulletin 78-12B " Atypical Weld Material in Reactor Pressure-Vessel Welds" dated March 19, 1979.
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The licensee's responses to this Bulletin dated November 22, 1978 and May 23, 1979 were reviewed. The licensee has submitted a report to the NRC dated April 24, 1979, certifying that no deviations had been identified for the reach Bottom Atomic Power Station Unit 2 and Unit 3 reactor vessels. Additionally, the licensee has archive weld deposit material in storage in the event any verification tests are required. The inspector had no further questions on this item.
Final PORC review is documented in PORC Minutes 79-69 dated July 5, 1979.
IE Circular 79-02 " Failure of 120 Volt Vital AC Power Supplies" dated January 16, 1979.
The inspector reviewed the results of the licensee's engineering review which determined that time delay circuitry is not used in Peach Bottom inverter units and that DC input voltage is limited by the circuitry in the battery chargers. Additionally, an alternate 120 volt source is not used in the design.
IE Information Notice 79-18 " Skylab Re-entry" dated July 6, 1979.
The inspector verified that PORC members had received this notice and that the licensee's contingency plans had been reviewed.
7.
In-Office Review of Monthly Operating Reports The following licensee reports have been reviewed in office.
Peach Bottom Atomic Power Station Monthly Operating Reports for:
June, 1979 dated July 10, 1979 This report was reviewed pursuant to Technical Specifications and verified to determine that operating statistics had been accurately reported and that narrative summaries of the month's operating experience were contained therein.
No unacceptable conditions were identified.
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TilIS PAGE INTENTIONALLY LEFT BLANK, IT CONTAINED 2.790 INFORMATION, NOT FOR PUBLIC DISCLOSURE.
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e 9.
Exit Interviews During the period of the inspection, licensee management as identified in Detail 1, was periodically notified of the preliminary findings by the resident inspector as documented elsewhere within this report. A summary was also provided to the licensee at the conclusion of the report period.
The licensee acknowledged inspection findings.
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