IR 05000277/1979005
| ML19289E802 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/11/1979 |
| From: | Greenman E, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19289E796 | List: |
| References | |
| 50-277-79-05, 50-277-79-5, 50-278-79-04, 50-278-79-4, NUDOCS 7905290120 | |
| Download: ML19289E802 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-277/79-05 Region I 50-278/79-04 RW h SCw277 Docket No.
Sn_979 DPR-44 C
License No.
DPR-5G Priority Category C
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Licensee:
Philadelohia Electric Comoany 2301 Market Street Philadelohia. Pennsylvania 19101 Facility Name:
Peach Bottom Atomic Power Station Units 2 and 3 Inspection at: Delta, Pennsylvania Inspection conducted: January 29 - February 2, 1979 Inspectors:
YMI 4//o/79 E. G. Greenman, Reactor Inspector date signed
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Other Personnel date signed E. J. Brunner, Chief, RO&NS Branch
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da e signed Approved by:
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f E. C. McCa'be, Jr., Cnief, Reactor Projects date signed Section No. 2, RO&NS Branch Inspection Summary:
Inspection on January 29-February 2, 1979 (Combined Report Nos. 50-277/79-05 and 50-278/79-04)
Areas Inspected: Routine, unannounced inspection by one regional based inspector of plant operations, facility tours, IE Circular followup, LER review in office and on site, followup on previously identified unresolved items and independent effort. The inspection irvolved 18 inspector-hours on site at Unit 2 and 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> on cite at Unit 3 by one NRC inspector and Regional Management.
Results: Of the six areas inspected, no items of noncompliance were identified.
2047 J37 Region I Form 12 7905290120 (Rev. April 77)
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DETAILS Persons rontacted
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R. S. P
..hmann, Assistant Station Superintendent M. J. Ulirich, Station Superintendent Other licensee employees were contacted during the inspection.
These included engineering personnel, administrative personnel, reactor operators, shift supervision, security personnel and health physics personnel.
- denotes those present at the exit interview.
2.
Previous Inspection Item Update (0 pen) Unresolved item (277/77-38-05): Unit 2D RHR pump foundation cracking.
The licensee inspected the Unit 2 and Unit 3 RHR Pump Pedestals on October 31, 1978.
Previous cracking on the 2D RHR pump foundation had been identified.
Inspection findings at Unit 2 included small cracks at three of four corners for Pumps A, B and C.
The 2D pump has cracks at all four foundation corners but inspection indicated no apparent change since the 1977 inspection of this foundation.
At Unit 3 minor cracking of the foundations was identified for the 3B, 3C and 3D pumps.
The 3A foundation has two broken corners, has cracks at all four corners and one crack in the middle of one side of the foundation. All base bolts for the RHR pumps were torqued to within the acceptance criteria of 340 ft/ pounds 168 ft pounds. The licensee's evaluation indicates no corrective action is required. The foundations are 10.5 inches thick and 51 inches square reinforced concrete.
The inspector noted that on September 28, 1977 only the 2D RHR pump foundation showed evidence of cracking.
This item remains unresolved pending review of the licensee's final report of calculations, assumptions and stresses to assure that structural integrity is adequate.
3.
Facility Tour Facility tours were conducted at both Unit 2 and Unit. 3 on numerous occasions during the course of this inspection. Areas examined included the turbine building, reactor building, control room, radwaste and exterior areas including access controls.
Inspections were condiacted during 30 minute intervals to observe access control over parcels entering the turbine building.
Inspections were also conducted to determine the general state of cleanliness, housekeeping, adherence to fire protection guidelines and to observe plant conditions.
The 2047 J38
inspector checked equipment status and operability and verified by comparison of selected control room instrumentation that limiting conditions for operation were being satisfied. The status of off normal alarms wue discussed with various operating personnel.
Operators were knowledgeable of plant conditions.
Minimum staffing requirements were also verified based on control room observations.
During the course of tours, various high radiation area doors were checked to confirm that they were locked as required.
Selected locked valves were also verified.
No unacceptable conditions were identified.
4.
Non Routine Event Review The inspector reviewed the follcwing non routine events both in office and on site for safety significance, circumstances and relationship to Technical Specification protective limits.
The licensee's review, evaluation and corrective action was also reviewed.
LER Number 2-79-6/lP -
Unit 2 and Unit 3 Recirc MG set room fire protection system was out of service for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with no fire watch posted.
2-79-7/IP -
SGTS Fire Protection System was cut of service for approximately 8 days.
3-79-1/3L-0 - Recorded Hi Hi trip value for one mainsteam line radiation monitor was 50 mr greater than T.S. limit.
3-79-4/03L-0 - Setpoint of one switch interlock to indicate core spray pump running for ADS actuation was found 0.2 psig greater than allowable during surveillance.
5.
IE Circulars Which Reouire No Response Inspection was performed for the following IE Circulars to verify whether: the Circular was received by licensee management, review for applicability was performed, corrective action (if any) was initiated and/or evaluated and supporting dncumentation evidencing licensee review was contained in PORC minutes.
"indings were as follows:
a.
IE Circular 78-15 - Tilting Disk Check Valves Fail to Close With Gravity in Vertical Position The licensee utilizes Clapman tilting disk check valves.
Clapman valves are designed to be installed only in the horizontal position.
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The Technical Engineer verified that the subject valves were all properly installed in the horizontal plane. The verification was performed by visual inspection of accessible check valves and eyamination of piping plans and section drawings for inaccessible valves.
b.
IE Circular 78-16 - Limitoroue Valve Actuators Engineering reviews disclosed no generic difficulties with these actuators at Peach Bottom. The licensee considered incorporation of operating methods recommended by Limitorque associated with usage of the declutcher during motor operation, manual valve seating and electrical stroking subsequent to use of the manual actuator. The operating group does not try to engage the clutch manually with the motor running nor is it accepted practice to
" bump" motors or manually jack valves on to the seat. The licensee is modifying maintenance procedures to indicate that motors must not be operated while holding the clutch lever.
6.
Exit Interviews At periodic intervals during the course of this inspection, meetings were held with facility senior management, denoted in Detail 1, to discuss inspection scope and findings. A licensee representative acknowledged inspection findings.
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