IR 05000293/1978025
| ML19269B987 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/22/1978 |
| From: | Architzel R, Foley T, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19269B979 | List: |
| References | |
| 50-293-78-25, NUDOCS 7901190183 | |
| Download: ML19269B987 (12) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
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0FFICE OF INSPECTION AND ENFORCEMENT Region I
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Report No.
50~293/78-25 50-293 Docket No.
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License No.
Priority Category Licensee:
Boston Edison Company M/C Nuciear 800 Boylston Street Boston, Massachusetts 02199 Facility Name:
Pilgrim Nuclear Power Station, Unit 1 Inspection at:
Plymouth and Boston, Massachusetts Inspection conducted: October 22 4, 30-31 and November 1-3, 1978 Inspectors:
[
Ii73
//[.4!7f R. Architze','Rdact6r Inspector
'date signed AL,
// f.2Rl78
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T. Foley, Reactof Inspector 8 ate ' signed date signed Approved by:
@ db h h.2l-Q E. C. McCabe, Jr., Chief, Reactor Projects date signed Section No. 2, RO&NS Branch Inspection Summary:
Inspection on October 22-24, 30-31 and November 1-3, 1978 (Recort No. 59-293/78-25)
Areas Inspected:
Routine, unannounced inspection of plant cperations, organi-zation and administration, B Standby Diesel Generator repair, IE Circular review, and licensee action on previous inspection findings.
NRC in-office re'iew was documented. Facility tours were conducted.
The inspection involved 67 inspector-hours onsite and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at the corporate offices by two regional based NP' inspectors.
Results: Of the four areas inspected, no items of noncompliance were identified in three areas; one apparent item of noncompliance (Infraction - failure to follow procedure - Paragraph 4) was identified in one area.
Region I Form 12 7901196/fr3 (Rev. April 77)
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DETAILS 1.
Persons Contacted The following technical and supervisory level personnel were contacted:
R. Atkins, Station Electrical Engineer
- H. Balfour, Methods, Training and Compliance Group Leader E. Cobb, Chief Technical Engineer D. Hughes, Assistant to CTE R. Kennedy, NSRAC Secretary J. Keyes, Licensing Engineer, Plant Support Group A. Littlefield, Emergency Diesel Consultant S. Little, Licensing Engineer, Plant Support Group C. Mathis, Senior Plant Engineer
- P. McGuire, Station Manager M. McLoughlin, Senior Plant Engineer J. Nicholson, Assistant to Plant Superintendent R. Sevigny, Chief Maintenance Engineer E. Ziemanski, Licensing Engineer, Plant Support Group Other licensee employees were also interviewed.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findinos (Closed) Follow item (77-27-01): Procedure 8.M.3.1 acceptance criteria.
This procedure was revised (Revision 3, dated May 17, 1978) to include time frame acceptance criteria.
(Closed) Open item (78-05-01): The inspector reviewed Drawing E-228 -
Sheet 15, revision El which now shows the as-built condition of penetration Q1028.
(Closed) Unresolved item (78-01-08): The inspector reviewed the licensee's exposure records for the individual and a copy of his termination letter dated February 17, 1978.
(Closed) Unresolved item (78-14-05): NSRAC reviewed their subcommittee's memorandum documenting a review of safety evaluations in meeting 78-4 held on May 17, 197.
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(Closed) Noncompliance (78-14-01): Failure to specify Part 21 applicability on Procurement Documents.
The licensee responded to this item in a letter dated June 19, 1978.
The inspector reviewed purchase orders issued subsequent to September 1,1978 and verified that the documents specified the applicability of 10 CFR 21 require-ments.
(Closed) Follow item (78-19-02): Procedure 1.3.4 has been revised (Revision 18 dated September 5,1978) to delete the requirement for placing a vertical line adjacent to procedure revisions.
(0 pen) IE Bulletin 78-04:
The NRC has evaluated the adequacy of the licensee's response.
The inspector informed the licensee of the NRC position ~ ~.at stem mounted limit switches providing position indication must
. qualified.
The licensee stated that the stem mounted limit sv.tches utilized on the main steam line isolation valves would be replaced during the next scheduled refueling outage.
This Bulletin will remain open pending completion of the licensee's actions.
(Closed) Noncompliance (78-18-01): No licensee response was required for this item.
The inspector reviewed procedure changes (8.M.2-2.10.2-10 through 15) specifying correct LPCI pump start times.
3.
B Star.dby Diesel Generator Repair a.
The "B" Standby Diesel Generator failed during surveillance testing on October 11, 1978 when the reactor was shutdown to replace the "C" safety-relief valve.
Failure was attributed to a short circuit between the generator stator windings and the casing iron.
The licensee determined the failure on stator phase "A" to have been caused by a loose piece of iron.
The inspector examined the fault in the coil which resulted in a short circuit. A portion of the licensee's repair procedure included a Maintenance Request (MR 78-2416) to repair loose or damaged core laminations on the stator.
The inspector reviewed testing and maintenance work in progress on the diesel generator as described belo.
b.
The following records associated with the generator repair
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were reviewed.
"B" Diesel Generator Repair Log Book, 10/1126/78
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"A" an; "B" EDG Maintenance History Cards (1972 to 10/1978)
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MR 78-2395, Remove Windings From Stator, 10/13/78
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MR 78-2384, Diesel Generator "B" Tripped, 10/11/78
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MR 78-2460, Rewind "B" Emergency Diesel Generator, 10/18/78
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(implemented General Electric Work Specification 3680,
" Winding Instructions on Electric Products Synchronous Generator S/N 16910018... Pilgrim Station" dated 10/17/78; and Addendum 1, " Test Procedure on Rotating Field," dated 10/23/78)
MR 78-2416, " Repair Loose or Damaged Core Laminations on
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B EDG Stator, 10/15/78 (implemented Electric Products Co.
Work Instructions, " Repair of Loose Tooth Laminations, BECo Pilgrim I," dated 10/14/7G and, Addendum 1, " Core Treatment on Synchronous Generator")
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General Electric Coil Technical Service Letter to Boston
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Edison, dated 10/23/78, certifying manufacturing sequence of stator coils, testing, and that manufacture was accom-plished to original specifications or better.
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Specification for Standby Diesel Engine Generators, Pilgrim Station, No. 600, dated 4/21/69.
In addition to a record review the inspector observed work and testing in progress.
Testing included phase to phase delta and wye connection resistance measurements, phase to ground, phase to phase (unconnected) high potential insulation resistance, polari-zation index determination and " donut" testing (to determine correct no. of windings per phase).
Surveillance Testing of the reassembled machine and total loss of offsite power testing was accomplished prior to restart on October 27, 1978.
This area (78-25-01) will be re-examined to ensure that quality related records are permanently maintaine *
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4.
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 plant systems and conditions and to observe activities in progress.
The plant areas inspected included the Control Room, Turbine Building, Augmented Off Gas Building, accessible portions of the Reactor Building, the new security building (under construction), and a perimeter walk down.
The following were among the items observed:
Radiation controls properly established;
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Housekeeping, including attention to the elimination of
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fire hazards; No fluid leaks of significance;
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Pipe vibration, including the condition of hangers and seismic restraints; Status of preselected locked valves;
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Equipment tagging for compliance with administrative
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requirements;
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Control Room manning in accordance with Technical Specifi-cation requirements; and,
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Reasons for lighted annunciators in the Control Room.
No items of noncompliance were identified.
b.
Review of Operating Records (1)
References Pilgrim Nuclear Power Station Administrative Pro iures
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1.3.2 Special Orders 1.3.4 Procedures
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1.3.16 Conduct of Personnel in Control Room
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1.3.17 Manning of Control Room
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1.4.6 Housekeeping
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2.1.10 Computer Data and Alarms
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2.1.16 Nuclear Plant Operators Tour
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1.4.5 Station Tagging Procedures (2) The inspector reviewed the following logs and records; Chief Operating Engineers Instruction Log
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Watch Engineers Log September 10-30, 1978
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Nuclear Plant Operators Logs October 1-23, 1978
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Operations Daily Surveillance Log October 1-20, 1978 Station Operations Log September 10-30, 1978
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Balances of Plant Printout (selected dates in October
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1978)
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NSSS Alarm Typer (selected dated in October 1978)
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Failure and Malfunction Reports 78-75 (8/2/78) through 78-96 (10/11/78)
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Scram Reports 78-1 through 78-9 The logs and records were reviewed to verify that:
Log sheet entries were properly filled out and initialed
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Log ertries involving abnormal conditions are sufficiently detailed Log book reviews are being conducted by the staff
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Operating orders do not conflict with the intent of the Technical Specifications (TS)
Jumper log entries do not conflict with the TS.
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One item of noncompliance and two unresolved items were identified as described in paragraphs 4.c, d and e below.
c.
During the course of the record reviews documented above, the inspector noted four different methods used to correct errors in quality records:
covering with white opaque correction fluid
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covering with white tape writing over the error
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lining out the error and initialing
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The inspector brought this matter to the licensee's attention.
The licensee stated that the correct / preferred method for making corrections to quality records would be specified.
Until the licensee's actions have been completed and reviewed, this item (78-25-02) is considered unresolved.
d.
During a review of the PNPS Operations Daily Surveillance Logs (OPER-09) the inspector noted the following items regarding their completion:
Several tests (Nos. 11, 14, 21, 27 and 29) do not specify
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action to take if test results are unsatisfactory.
Several tests (Nos. 9,12,16 (Data Collection), and 28) do
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not specify that they do not have to be performed when shut-down.
(Test 28 is also required when greater than 212 F.)
Several tests (Nos. 12,16 (4.1.B), and 18) do not have a
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place for reviewer signature.
Test 15 (Check Refueling Area Exhaust Monitor) requires
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clarification of perfonnance of upscale and downscale trips.
The licensee stated that procedure 2.1.15 would be revised to correct these items. This item (77-25-03) is unresolved pending the licensee's action.
e.
During a review of the Chief Operating Engineer's (C0E) Instruction Log the inspector noted the following entry on October 27, 1978:
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"Perfom 8.A.9.A, Turbine Stop Valve and Control Valve at 70%
and every 5% up to and including 90%.
If swings too erratic, cancel tests."
While perfonning the above referenced testing at 80% power on October 30, 1978, the reactor scrammed (APRM High Flux). The licensee attributed the scram to sluggish control valve response.
Testing had been completed at 70% and 75% power.
The inspector noted a prccedural restriction prohibiting completion of this testing at greater than 70% power.
The inspector further noted that a procedure change had not been issued, nor a temporary procedure change (SR0 Change) initiated to perform this testing at greater than 70% and that the C0E Instruction Log was not an acceptable vehicle for procedure changes.
This is an item of noncompliance (77-25-04).
5.
Organization and Administration The inspector reviewed licensee records and interviewed licensee per-sonnel to ascertain whether the onsite organization and administration were in conformance with the technical specifications. The following areas were examined:
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Onsite organization as described in Figure 6.2.2 of the Technical Specifications.
Personnel qualification levels in confomance with ANSI N18.1,
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1971, requirements.
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Authorities and responsibilities of licensee personnel.
Operations Review Committee (0RC) and Nuclear Safety Review and
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Audit Committee (NSRAC) membership and qualifications.
Changes in organization and structure reported to the NRC.
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No items of noncompliance were identified, however, an unresolved item was identified as described in paragraphs below.
Paragraph b. below describes recent organizational changes.
a.
The NSRAC documents their collective competence in various dis-ciplines with a competence matrix maintained by the NSRAC Secretary.
The inspector reviewed a memorandum dated February 28, 1978 identifying a lack of metallurgical expertise. The memorandum
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stated that the combined expertise of the connittee was normally sufficient; however, the NSRAC would utilize a consultant or a disciplined engineer when required.
The inspector further noted that for the areas of Electrical Engineering and Fire Protection no regular members were recorded as providing expertise. The licensee stated the NSRAC competence in these areas will be evaluated.
This item (78-25-05) is unresolved.
b.
The following represents current facets of the licensee's organization:
(1) Onsite Mr. H. Calfour has replaced Mr. S. Martin as Methods,
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Training and Compliance Group Leader Messrs. C. Van Trease (Chief Technical Engineer) and
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M. Hench (Chief Radiological Engineer) have replaced Mr. M. Naughton, CTE.
LER 78-047 described creation of the position of Chief Radiological Engineer and the addition of staff positions for an ALARA Engineer and Waste Management Engineer.
(2) NSRAC The current membership of the NSRAC is as follows:
W. Sides, Quality Assurance Manager, Chairman S. Rosen, Nuclear Engineering Manager, Vice Chairman G. Andognini, Nuclear Operations Manager P. McGuire, Pilgrim Station Superintendent W. Larson, System and Safety Analysis Group Leader J. Candon, Principal Engineer, Yankee Atomic Electric Company No unacceptable conditions were identified.
6.
IE Circular Review The following IE Circulars were reviewed on site to determine that the circular was received by licensee management, a review for applicability was performed, and that further action taken or planned was appropriate.
No unacceptable conditions were identifie.
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78-12, Proper Lubricating Oil for Terry Turbines
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78-03, Packing Greater than Type A Quantities of LSA Materials
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78-11, Recirculation M-G Set Overspeed Stops
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78-12, HPCI Turbine Control Valve Lift Rod Bending 78-13, Inoperability of Service Water Pumps
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78-14, HPCI Turbine Reversing Chamber Hold Down Bolting
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Actions associated with Circulars 78-12 and 14 are scheduled to be accomplished during the next refueling outage.
The inspector reviewed a Chief Maintenance Engineer memo 78-57 documenting this work planning.
These circulars will remain open pending work completion.
7.
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 78-028/03L 6/22/78 Fuel Pool Cooling System Weld Crack 78-036/03L 8/9/78 Suppression Chamber Purge Exhaust Valve Failed to Close 78-038/03L 8/31/78 Drywell to Torus Differential Pressure Limit Not Met 78-039/03L 8/31 /78 B Emergency Diesel Generator Inoperable 78-041/03L 9/8/78 Reactor Pressure Switch Set-point Drift 78-043 9/19/78 Refuel Floor Exhaust PRM Inoperable 78-044/03L 9/21/78 Torus Water Temperature Exceeded LC0
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78-045/03L 10/24/78 Torus Water Temperature Indicator Inoperable 78-046/03L 11/2/78 0xygen Analyzer Valve Dosition Indication 78-047/03L 11/2/78 Station Organization Change b.
NRC:RI in office review of the following reports has been com-pleted with no unacceptable conditions identified:
AL*Jst 1978 Monthly Report (BECo Letter 78-167)
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September 1978 Monthly Report (BECo Letter 78-177)
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8.
Onsite Review In addition to the in office review described in Paragraph 7.a above, the following LERs were reviewed onsite.
78-049/03 L B Emergency Diesel Generator Inoperable
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78-047/03L Station Organization Change
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78-048/03L Blowdown
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Licensee's actions concerning LERs78-049 and 78-047 are described in Paragraphs 3 and 5, respectively.
LER 78-048 described a blowdown following a reactor scram on October 9, 1978. The licensee informed the NRC of this event by telephone on October 13, 1978.
While changing a lightbulb indicating auxiliary transformer voltage, the socket broke and grounded to the panel.
This activated the differential overcurrent relay logic and resulted in a load reject scram.
Relief / Safety Valves "A" and "C" opened.
"A" subsequently closed, however, "C" stayed open.
This resulted in a temperature drop of approximately 95 F in 20 minutes.
At 330 psig,
"C" valve closed and temperature (pressure) were allowed to increase to minimize the effects of the blowdown.
At approximately 630 psig
"C" valve again reopened for another 20 minutes, resulting in a cooldown of 85 F, when it reseated "C" Safety / Relief valve was replace '
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The inspector reviewed the failure and malfuction and scram reports associated with the event and also examined traces of the recirculation loop temperature and vessel to flange temperature recorders.
The ORC had reviewed this event in meeting 78-47.
The inspector noted that the 100* F cooldown limit had not been exceeded during any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> interval and that the vessel flange temperature had not exceeded 100 F (T.S. Limit 145 F).
No unacceptable conditions were identified.
9.
Unresolved Item An item about which more information is required to determine acceptability is considered unresolved.
Paragraphs 4 and 5 contain unresolved items.
10.
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 and unresolved item were identified.