IR 05000293/1979016
| ML19256F092 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/30/1979 |
| From: | Architzel R, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256F085 | List: |
| References | |
| 50-293-79-16, NUDOCS 7911210348 | |
| Download: ML19256F092 (7) | |
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e U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF TNSPECTION AND ENFORCEMENT Region I Report No. 50-241/74-16 Docket No. 50-293 License No.
DPR-35 Priority
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Category c
Licensee:
Boston Edison Company M/C Nuclear 800 Boylston Street Boston, Massachusetts 02199 Facility Name:
Pilgrim Nuclear Power Station, Unit 1 Inspection at:
Plymouth, Massachusetts Inspection conducted:
August 7-10, 1979
. Inspectors:
8 0. A U.)*'- i b 9 k88 h S H. Arc.iltzel, Reactor Inspector date signed date signed date signed
. Approved by:
f. C. k O.
9 f'I !N E. C. McCabe, Jr., Chief, Reactor Projects date signed Section No. 2, RO&NS Branch Inspection Summary:
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Inspection on August 7-10,1979 (Report No. 50-293/79-16)
Areas Inspected: Routine, unannounced inspection by. one NRC regional based inspector (28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />) of plant operations. A facility tour was conducted and NRC in office review of licensee reports was documented.
Noncompliances:
One (Infraction - violation of primary containment integrity,
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Paragraph 2.c).
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Region I Form 12
(Rev. April 77)
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DETAILS 1.
Persons Contacted The following technical and supervisory level personnel were contacted:
- J. Alukonis, Watch Engineer E. Cobb. Chief Operating Engineer J. Dolan, Maintenance Staff Engineer
- J. Fulton, Senior Plant Engineer P. McGuire, Station Manager
- R. Sevigny, Chief Maintenance Engineer
- C. Van Trease, Chief Technical Engineer
- denotes those present at the exit interview.
Other licensee employees were also interviewed.
2.
Review of Plant Operations a.
Plant Tour The inspector conducted tours of the accessible plant areas listed below at various times to observe the status of piant systems and conditions and to observe activities in progress.
The plant areas inspected included the Control Room, Intake Structure, accessible portions of the Reactor Building and the Auxiliary Bay.
The following were among the items observed:
Radiation controls properly established;
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Housekeeping, including attention to the elimination of fire
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hazards; No fluid leaks of significance;
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Pipe vibration, including the condition of hangers and
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seismic restraints; Status of preselected locked valves, jumpers;
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Equipment tagging for compliance with administrative require-ments;
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Control Room manning in accordance with Technical Specifica-
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tion requirements;
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Reasons for lighted annunciatces in the Control Room; Status of repairs to the shorefront breakwater;
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Work in progress to repair the intake structure screens;
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and, Inspection tags on fire extinguishers, no obstruction of
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fire hoses, etc.
No items of noncompliance were identified.
b.
New Security Building The inspector received indoctrination training concerning use of the new security building, including access control considera-tions within the plant.
This training included tours of the CAS and entire Security Building.
No items of noncompliance were identified.
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c.
Review of Operating Records The inspector reviewed the following logs and records:
Chief Operating Engineers Instruction Log, April 6, 1979 -
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August 8, 1979; Watch Engineer's Memorandum Book, April 30 - August 8, 1979;
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Operations Daily Surveillance Log, August 2-7, 1979;
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Station Operations Log, June 9-21, 1979;
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Jumper and Lifted Lead Log - all active entries; and
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Failure and Malfunction Reports:
Number Date Description 79-54 6/18 APRM Channel F Inhibit Switch Inoperable 1380
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79-53 6/17 APRM F 1/2 Scram 79-52 6/17 IRM Channel A Downscale 7 9-51 6/16 MSLIV 1 A and 1C Slow Closing Time 79-50 6/10 SBGTS Fan Belt Broken 79-49 6/6 Radioactive Spill While Splitting Cask 7 l-48 6/6 C Main Steam Line Radiation Monitor Reading High 79-47 6/5 Refueling Floor Ventilation Monitor Test Switch Failure 79-46 5/31 Main Stean Line Radiation Monitor Downscale 79-45 5/29 A IRM Downscale 79-44 5/27 SSW Crosstie MOV Breaker 79-43 5/24 E RBCCW Pump Discharge Gage Failed 79-42 5/21 Control Rod 34-51 Drift
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79-41 5/19 Primary Containment V'^1ation 79-40 5/19 Start A Recirculation Pump with Delta T > 50 F 79-39 5/17 RBCCW Pump Discharge Gage 79-38 5/16 B Diesel Pre-Lube Pump Tripped 79-37 5/15 MS Line Drain Valve 220-1 79-36 5/12 Snubber Found Disconnected Temporary Procedures:
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79-21, dated August 2,1979; To Verify Compliance with
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IEB 79-14 79-20, dated July 29, 1979; CRD Cellet Finger Flushing
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79-19, dated June 29, 1979; Auto Start HPCI Turbine
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(10% Open Steam Inlet Valve)
The logs and records were reviewed to verify that:
Log sheet entries were properly filled out and initialed
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Log entries involving abnormal conditions are sufficiently
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detail ed Log book reviews are being conducted by the Staff
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Operating orders do not conflict with the intent of the
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Technical Specifications (TS)
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Jumper log entries do not conflict with the TS
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NRC reporting requirements are satisfied
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. Plant operations are in conformance with the Limiting Conditions
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for Operations (LCO's) of the TS.
One item of noncompliance was identified as described in Paragraph d below, d.
Primary Containment Integrity Violation The inspector questioned the licensee concerning an entry (at 1920 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.3056e-4 months <br />) on June 12, 1979.
The entry discussed the stationing of an extra operator in the control room to provide a minimum flow path for A and C Low Pressure Coolant Injection (LPCI) pumps while the "A" Core Spray Loop was made inoperative to repair the 6 inch check valve N238M4 under Maintenance Request No.
79-1231.
The inspector reviewed Piping and Instrumentation Drawing No. M-242 and determined that the downstream portion of this piping entered the TORUS directly without further isolation, and that the pipe outlet was indicated open ended and submerged under normal TORUS water level.
The inspector reviewed the following documents associated with the repair of check valve N238M4:
Maintenance Request No. 79-1231 dated May 30, 1979, Investigate
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Problem with Core Spray Loop A Minimum Flow Line, and associated Maintenance Summary and Control Form and Work Request Permit.
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Station Operations Log, June 11,12 and 13.
ORC Meeting No. 79-29, Minutes dated May 30, 1979.
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Alternate System Surveillance Tests completed pursuant to Procedure 8.5.1.4 (LPCI, Manual Start Diesel, HPCI, B Core Spray Loop) on June 11,12 and 13.
Although the Maintenance Requast was reviewed by the originator (Control Room Supervisor), initialed by a Watch Engineer, work described by a Maintenance Staff Engineer, approved by the Chief Operating Engineer, Chief Maintenance Engineer, Quality Control, on shift Operating Supervisor, Watch Engineer and Licensed Operator 1380 141
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placing safety tags, apparently all failed to realize that repairing the six inch check valve at power was a violation of primary containment integrity.
Personnel interviewed by the inspector indicated that they were knowledgeable of where the pipe ended (under TORUS water level by 11 inches). The water seal provided protection for the worker from the containment Nitrogen atmosphere, however, would have resulted in a direct six inch path from the TORUS to the Reactor Building Atmosphere ("A" RHR Quadrant) during a LOCA or any containment pressurization sufficient to overcome the 16 foot elevation loop seal.
When the licensee was made aware of the containment integrity aspects of this repair Licensee Event Report 79-029 was submitted on August 9, 1979. This is an item of noncompliance (293/79-16-01).
On August 10, 1979, Region I issued an Immediate Action Letter to Boston Edison Company specifying the following actions:
(1) Review of the sequence of events leading to the violation of the primary containment integrity, determine the safety significance of each of these events and define specific measures to prevent recurrence; (2) Review the adequacy of procedural and management controls as they apply to safety-related maintenance; and, (3)
Review the adequacy of plant staffing and staff training to prevent such an occurrence.
This licensee agreed to complete the reviews and inform Region I in writing of the substance of the reviews and of any changes or improvements in his programs as a result of the reviews by August 17, 1979.
3.
Organization Changes During the conduct of the inspection, the inspector was informed of the following planned or existing changes in the licensee's organization:
Effective April 17, 1979, Mr. T. Galligan was appointed Chairman of
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the Board and Chief Executive Officer.
Effective April 17, 1979, Mr. F. Staszesky was appointed President and
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Chief Operating Officer.
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Effective May 1,1979, Mr. Andrew Corry was appointed Senicr Vice
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President (Electrical, Steam, Nuclear, Environmental, Planning,
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Research).
Effective August 13, 1979, Mr. R. Machon became Assistant Station
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Manager (a new position).
Effective September 1,1979, Mr. M. Feldman, Senior Vice President
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will retire.
No unacceptable conditions were identified.
4.
NRC In Office Review a.
NRC:RI in office review of the following LERs has been completed with no unacceptable conditions identified:
LER Dated Subject 79-015 May ll, 1979 RCIC Inoperative *
79-013 April 26, 1979 Setpoint Drift DW to TORUS Differential Pressure Transmitter 79-016 May 23, 1979 Snubber Inoperable, A Feedwater Line 79-020 July 9, 1979 SBGTS Inoperable
- This LER was also reviewed onsite to ensure that the RCIC system was restored to operation within the required seven days (actually 1 day).
b.
NRC:RI in office review of the following reports has been completed with no unacceptable conditions identified:
April,1979, Monthly Report (BEco Letter No. 79-88, dated May 8,
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1979)
May,1979, Monthly Report (BECo Letter No.79-115, dated June 11,
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1979)
June, 1979, Monthly Report (BECo Letter No.79-141, dated July
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12, 1979)
5.
Exit Interview At the conclusion of the inspection, the inspector held a meeting (See Paragraph 1 for attendees) to discuss the inspection scope and findings.
The item of noncompliance was identified.
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