IR 05000293/1979003
| ML19270G579 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/23/1979 |
| From: | Architzel R, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19270G575 | List: |
| References | |
| 50-293-79-03, 50-293-79-3, NUDOCS 7906140113 | |
| Download: ML19270G579 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
79-03 Docket No.
50-293 License No.
DPR-35 Priority
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Category C
Licensee:
Boston Edison Concany M/C Nuclear 800 Boylston Street Boston, Massachusetts 02199 Facility Name:
Pilgrim Nuclear Power Station, Unit 1 Inspection at: Plymouth and Boston, Massachusetts Inspection conducted:
February 13-16, 1979 Inspectors:
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3//9/?f R. Architzel, Reactor inspector date signed date signed date signed Approved by:
C 0.. b 0+1, L 3 I23179 E. C. McCabe, Jr., Chief, Reactor date signed Projects Section No. 2, RO&NS Branch Inspection Summary:
Inspection on February 13-16,1979 (Report No. 50-293/79-03)
Areas Inspected:
Routine, unannounced inspection of IE Bulletins and Circulars aiid licensee action on previous inspection findings.
A facility tour was conducted.
The inspection involved 22 inspector-hours onsite and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at the corporate office by one NRC inspector.
Noncompliances:
None 2270 020 7 906140 \\G 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 G. Anderson, Watch Engineer W. Armstrong, Assistant to Nuclear Operations Manager
- H. Balfour, Methods, Training and Compliance Group Leader E. Cobb, Chief Operating Engineer J. Fulton, Senior Plant Engineer D. Hughes, Assistant to COE J. Keyes, Licensing Engineer
- J. Nicholson, Assistant to Plant Superintendent W. Olsen, Trailing Specialist C. Ondash, Senior Licensing Engineer P. Smith, I&C Supervisor E. Ziemianski, Senior Mechanical Engineer denotes those present at the exit interview
Other licensee employees were also interviewed.
2.
Licensee Action on Previous Insoection Findinas
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(0 pen) Unresolved Item (76-29-02):
RBCCW Alarm Condition and Off-Line Monitoring Capability.
The continuous alarmed condition of the Reactor Building Closed :ooling Water (RBCCW) process monitor was initially identified in Seatember,1976 (Report No. 76-25, Detail 4.b).
The cause was high radiation background near the installed detector. A reexamina-tion was made in November, 1976, by the NRC.
The licensee committed to sample the RBCCW weekly and sample daily the Salt Service Water, and stated that in off-line monitoring system would be installed to provide RBCCW process monitoring.
This system was installed to provide an indication to operations personnel of potential process system mal-functions by detecting an increase of radioactive material in the closed cooling water loops (reference FSAR Section 7.12.7.1).
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This item was reinspected in April, 1978 (NRC Report 78-09).
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The licensee stated that the PDCR was in the final conceptual design phase and implementation was scheduled for May,1978.
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Inspection during August,1978 (Report 78-17), and during the f*
current inspection revealed that no further action had been taken
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in this area.
During a subsequent telephone conversation on February 26, 1978, the licensee stated that the equipment was on order for
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this modification and that it would be installed by May 1,1978.
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The inspector acknowledged the licensee's comment, however, he ex-
pressed concern that implementatian of this modification had been
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delayed almost three years since its need was identified.
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-1 (Closed) Noncompliance (78-01-03):
Calibration of Reactor Recircula-
j tion Pumps Electrical Power Instruments.
The licensee's action
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relating to this issue had previously been examined during Acril,
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1978 (NRC Report 78-10). The pump power instruments were sc.c out
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for calibration and returned.
Calibration records were reviewed a;
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for procedure 3M3-ll, 12, 13 and 14 which were performed on October
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26, 1978, verifying calibration of the recirculation pump electrical
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instrumentation.
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(Closed) Noncompliance (78-16-01):
Stack Dilution Fan Dampers
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Closed.
The inspector verified the licensee's immediate action i
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during inspection 78-16.
Permanent corrective actions which were l
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committed to in the licensee's August 8, 1978 letter were verified,
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including verifying miminum air flow on a daily basis via the OPER-
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(0 pen) Noncompliance (78-16-02):
Operation with less than 2 IRMs in f
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RPS Trip System A.
The inspector verified that the licensee had taken or plans to take the actions stated in their response to this item
.y dated August 8, 1978.
This action included informing the individuals
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involved of the intent of TS 3.1, issuing a memorandum to licensed b-S individuals concerning the importance of literally adhering to Limiting g:
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Conditions for Operations and issuing a Clarification Memorandum (CM
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78-16, dated August 30, 1978) to all licensed personnel clarifying F..
the intent of TS Table 3.1.1.
The inspector reviewed the LC0 training
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scheduled for the operator qualification program and stated that this
e item would remain open pending completion of the additional training.
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(0 pen) Noncompliance (78-16-03): Maintenance Request Procedure Not h
Followed. The inspector verified that certain actions which had been
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committed to by the licensee in their response dated August 8, 1978 j
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had been taken.
This included issuing instructions to the Watch En-
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gineers and Operating Supervisors to verify package completeness and
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routing a revised procedure for review by those personnel responsible for Maintenance Requests (Routed January 9,1979).
The revision did not address expanding the work scope following QC review, an action which the licensee stated would be taken.
A major revision to procedure 1.5.3 was in progress during this inspection.
The licensee stated that this issue would be readdressed in a letter to the NRC following this inspection.
(Closed) Unresolved Item (78-17-02):
Technical Specification Clari-fications.
The inspector reviewed revised N0D procedure 19.06, Technical Specification Clarifications.
The procedure revision in-corporated additional steps defining the scope and required reviews for the approval of Technical Specification Clarification, including ORC g roval.
The inspector noted through a review of ORC meeting minutes that these documents are being approved by the Committee.
(0 pen) Noncompliance (78-18-02):
IRM Channel Calibrations.
The inspector noted that for startups performed subsequent to this item, Maintenance Requests had been utilized to document performance of the IRM upscale /downscale Rod Block checks (Review of MRs dated August 15 and September 15, 1978).
The inspector reviewed a new procedure, 78-54, "IRM Setpoint Checks" dated February 14, 1979.
Procedure 2.1.1 (Startup from Cold Shutdown) had not been revised to require performing IRM Rod Block Checks nor had a TS change request been submitted to specify clearly the IRM functional test and calibration requirements.
These actions were committed to in a telephone conversation between the Station Manager and an NRC regional inspector on September 19, 1978.
The licensee stated that a letter would be sent to the NRC further addressing their action regarding this item.
(Closed) Noncompliance (78-18-03):
Test Instruments Not Calibrated.
The inspector reviewed an internal audit of the BECo Standards Laboratory.
In those cases where the calibration tolerances were outside the BEQAM requirements, the inspector noted that the licensee had reviewed instances of instrument use and evaluated the measured parameters in accordance with the accuracy range of the standard utilized.
No unacceptable conditions were identified.
(Closed) Noncompliance (78-19-01):
Jumper Status Inaccurate.
The inspector verified the licensee's action as stated in their September 6,1978 letter.
The actions included an audit of current entries and a revision to procedure 3.M.1-3, Lifted Wire and Temporary Jumper (latest revision reviewed dated January 3,1979), to include additional controls of the placement and removal of jumpers.
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(Closed) Unresolved Item (78-25-01): Work Package for B Emergency Diesel Generator. The inspector reviewed the completed work package for the B Emergency Diesel Generator repair which had not been fully completed during inspection 78-25.
This included acceptable surveillance tests (run at full load one hour, total loss of offsite,
power) and completion of QC review.
No unacceptable conditions were identified.
(Closed) Unresolved Item (78-25-02):
Record Correction.
The inspector reviewed a procedure change to AP 1.3.7, Records, specifying the accepted method of correcting control room logs and record books.
(Closed) Unresolved Item (78-25-03):
Revise OPER-9.
The inspector reviewed revised Procedure 2.1.15, Daily Surveillance, dated February 1, 1979.
This procedure change incorporated the items addressed in report 78-25.
(Closed) Noncompliance (78-25-04):
Turbine Testing at Greater Than Allowed Power.
The inspector verified that instructions had been issued to Watch Engineers specifying the Limits of the COE Instruction Log and that the 0RC had reviewed this item (Meeting 79-01).
(Closed) Unresolved Item (78-27-06):
Setting of HPCI and RCIC System Tapes. The COE issued an Instruction Log entry (December 1, 1978) specifying that the controller setpoints would be set at or above Technical Specification requirements.
The ORC reviewed this item in Meeting 79-02.
The inspector checked the tape settings above TS requirements during this inspection.
(Closed) Unresolved Item (7827-05):
Elevator Key Control.
The inspector noted that the Elevator Key had been added to the Control Room key log and also noted that the elevator would not access the refuel floor during this inspection.
3.
Anticipated Transient Without Scram (ATWS)
The inspector reviewed (new) procedure 5.3.15, Reactor Isolation Without Scram or Loss of Offsite Power, dated February 9, 1979.
The inspector also reviewed the lecture plan for an ATWS situation and discussed this topic with the lecturer.
The first lecture for licensed operators had been given (February 9,1979) and all training is scheduled to be completed by April 8,1979.
The inspector noted that the licensee had utilized WASH-1270 and NEDC-20823 (G.E. Study of ATWS) for the preparation of the lecture plan.
No unacceptable conditions were identified.
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4.
IE Circular Review The following IE Circulars were reviewed on site to determine that the circular was recaived by licensee management, a review for ap-plicability was performed, and that further action taken or planned was appropriate.
No unacceptable conditions were identified.
78-CI-15, Tilted Disk Check Valves (0RC Meeting 78-37)
78-CI-17, Inadequate Guard Training (0RC Meeting 78-49)
78-CI-18, UL Fire Test (0RC Meeting 78-53)
All 3 circulars had been reviewed by +,he ORC, and action taken for circular 78-17 had been addressed via memorandum from the Site Security Supervisor to the Manager, Nuclear Operations.
The inspector reviewed this memorandum dated November 24, 1978, and verified that the concerns of the circular (guard training, docu-mentation, interviews with guards to verify training) were addressed.
For circulars 78-15 and 78-18, further review by the Nuclear Engineering Department was requested and was not yet completed.
These 2 circulars will remain open pending further review.
5.
Facility Tour
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Facility tours were conducted during the course of the inspection on February 13-16.
These tours included the Control Room, various levels of the Turbine Building, excluding the Condenser Compartment, the Diesel Generator Rooms, accessible areas within the Reactor Building and the Stores Building (new QC, Security and Training Offices).
Facility conditions were checked for general housekeeping, fire and safety hazards, radiation area access, monitoring equipment and selected equipment posi-tions.
The inspector questioned the licensee concerning the status (open) of the (20 inch) suppression chamber purge exhaust isolation valves.
In a letter dated January 9,1979 (response to NRR letter of November,1978, Containment Purging During Normal Plant Operations) the licensee stated that continuous purging through the suppression chamber exhaust isolation valves (2 inch line) was the normal mode of operation to maintain the required torus /drywell differential pressure.
The 20" valves do receive 2270 025 o
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an automatic closure signal when containment isolation is required and as stated in the letter, this flow path is utilized for de-inerting up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to/after a shutdown /startup.
One concern addressed in NRR's letter (dated November 29, 1978) is the ability of these vahes to close under the dynamic forces of a LOCA. The licensee took immediate action to close the 20 inch valves and instructions were issued via the COE Instruction Log Book to maintain these valves closed during power operation unless an operator is standing by the valve to close it.
These restric-tions would not apply prior to shutdown nor after startup as de-scribed in the licensee's November 29, 1978 letter.
This issue was discussed following the inspection with the Operating Reactors Project Manager for Pilgrim Nuclear Power Station.
This item is unresolved (70-03-01) pending reinspection by the NRC and implemen-tation of procedural controls by the licensee.
6.
IE Bulletin No. 78-14 - Deterioration of BUNA-N Components in Solenoids The inspector reviewed the action taken on the subject bulletin and the licensee's response dated February 2,1979 (BECo letter 79-33).
A member of the plant staff has been assigned responsibility for the implementation of the replacement program.
The licensee plans to replace the BUNA-N components in existing solenoids as a non-critical path item during outages (scheduled or unscheduled).
Approximately 50% of the repair kits are at the station a'nd the re-mainder on order with expected delivery by April,1979.
A total of 290 scram pilot valves, 2 discharge volume vent and drain valves, 2 backup scram valves and 1 test valve are affected.
This bulletin will remain open pending completion of the replacement program and initiation of the preventive maintenance program for the ASCO solenoid valves.
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NRC In Office Review a.
NRC:RI in office review of the following LERs has been com-pleted with no unacceptable conditions identified:
LER Dated Subject 79-003/03L February 12, 1979 Control Rod Drive Inoperable 79-004/04L February 13, 1979 Main Stack Process Radiation Monitor Sample Line Frozen 2270 026
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NRC:RI in office review of the following reports has been completed with no unacceptable conditions identified:
January,1979, ;ionthly Report (BEco letter 79-39,
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dated February 8,1979)
December,1978, Monthly Report (BECo letter 79-24,
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dated January 11,1979)
8.
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.
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