IR 05000320/1978024
| ML19224A199 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/23/1978 |
| From: | Durr J, Fasano A, Haverkamp D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19224A193 | List: |
| References | |
| 50-320-78-24, NUDOCS 7810190007 | |
| Download: ML19224A199 (22) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF, INSPECTION AND ENFORCEMENT Region I Report No.
50-320/78-24 Docket No.
50-320 License No.
DPR-73 Priority Category B2
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Licensee:
Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania 19603 Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
Middletown, Pennsylvania and Reading, Pennsylvania
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Inspection conducted: July 18-21 and July 313 August 3, 1978 Inspectors:
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u. a. H3verkamp, Heac or inspector date signed 0 A%<a_
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a. a. ea ano, neactor inspector Ja n s'igned b. n S
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yh 1. A. kebelowski, spactor inspector date signed
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Approved by:
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Ke
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.eactor Projects Section date sig'ned'
/No.1,
_ Bra Insoection Summary:
Insoection on July 18-21 and July 31-Aucust 3,1978 (Recort No. 50-320/78-24)
Areas inspected:
Routine, unannounced inspection by regional based inspectors of main steam relief valve / piping modifications; plant operations including shift logs and records and facility tour; licensee controls for nonroutine events; licensee followup actions concerning selected previous inspection findings, licensee events, and IE Bulletins and Circulars; measures established to implement Part 21 requirements; and selected licensee periodic and special reports. The inspection involved 93 inspector-hours onsite and two inspector-hours at the corporate office by four NRC regional based inspectors.
Results: Of the eight areas inspected, one item of noncompliance was found in one area (Infraction - failure to maintain the weld rod storage oven a' the required temperature - paragraph 3.c).
' I Region I Form 12 g$l61Ci000/
1-(Rev. April 77)
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DETAILS 1.
Persens Contacted Metropolitan Edison Comoany Mr. R. Pensel, Unit 2 Lead Electrical Engineer
- /**Mr. M. Bezilla, Unit 2 PORC \\ Secretary Mr. W. Conaway, II, Unit 2 Shift Foreman Mr. J. Chwastyk, Shift Supervisor
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- Mr. J. Floyd, Unit 2 Supervisor of Operations
- Mr. J. Hilbish, Station Lead huclear Engineer
- Mr. T. Mackey, Jr., Supervisor of Quality Control Mr. B. Mehler, Shift Supervisor Mr. I. Porter, Unit 2 Lead Instrumentation and Controls Engineer
- Mr. J. Seelinger, Unit 2 Superintendent-Technical Support Mr. J. Stair, Licensing Engineer
- Mr. R. Warren, Unit 2 Lead Mechanical Engineer General Public Utilities Service Corporation Mr. J. Godleski, QA Engineer Mr. W. Gunn, Site Project Manager Mr. T. Hawkins, Assistant Test Superintendent
- Mr. R. Toole, Test Superint.endent
- Mr. J. Wright, QA Panager
- Mr. L. Zubey, Mechanical' Engineer Crouse Nuclear Enerav Services Corporation
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Mr. H. Bailey, Project Manager
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The inspectors also interviewed several other licensee and contractor employees during the inspection.
technical and engineering staff personnel and general office pers
- denotes those present at the exit interview on July 21,1978. '
- deno'.es those present at the exit interview on August 3,1978.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (320/76-17-11):
Diesel generator "first out" failures.
Discussion with operations department personnel and observation 1.N
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n the control room and diesel generator rooms indicate that the icensee has the ability to analyze the incoming diese! alarms to
.cbtain "first-out" (sequence) infonnation.
(Closed) Inspector Followup Item (320/77-17-01):
IE Bulletin 77-01 followup. The licensee has identified the time delay relays in the diesel generators with regard to information received in IE Bulletin 7 7-01.
The relays were tested on a twice weekly basis during January and February.
The timing heads for 5 and SL relays were replaced and retested. The inspector had no further questions re-garding this item.
(Closed) Inspector Followup Item (320/77-28-06):
Possible RCP seal design deficiency.
A station blackout test was performed on April 22, 1978, and TP800/32, " Loss of Offsite Power Test," was reviewed and approved on May 19, 1978.
The procedure calls for the monitoring of the reactor coolant pump seals for pressure, inlet, and outlet temper-ature.
The inspectcr reviewed tne recorder charts and found no dis-crepancies.
The redesign of makeup lines to the seals and makeup pump sequence appears adequate. The inspector had no further questions on this item.
(Closed) Inspector Followup Item (320/77-29-04):
Dcmestic water syttem isolation.
TN licensee has completed the ECM's 5512, 8088, and 8638 that tie the domestic water system to the Nuclear River pumps prelube, Service River pumps prelube, and Service Water pumps prelube. Areas that are fed by domestic water have been capped and check valves installed to prevent backflow from the prelube systems.
The inspector had no further questions regarding this matter.
(Closed) Inspector Followup Item (320/77-40-02):
RCP leakage at pun.p volute.
Procedure SP710/?, HTX 147.36, test results were appraved on April 6,1978.
SP710/2, " Controlling Precedure for Post Fuel Load Precritical Testing," includes requirements for ob-servation of the mating flange of the volute and Reactor Coolant pump flange.
No leakage was observed. The inspector had no further questions cc:icerning this item.
(Clored) Inspector Followup Item (320/77-41-02):
Brush recorder sensitivity. The sensitivity band of the brush recorders has been narrowed in TP800/36, " Shutdown From Outside the Control Room."
Thus, a larger divisional increment will be obtained in the range of expected test data for Pressurizer Level, Reactor Coolant Pressure, and Reactor Coolant Loop Temperatures. The inspector had no further questions reg 2rding this item.
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(Closed) Unresolved Item (320/77-41-05): Modification of hanger suppnrt. The licensee has revised the hanger support design for NSH-281-5 (Engineering Change Memo, Serial No. 5612) to eliminate interference with electrical conduits. The inspector observed the modified hanger and found it in accordance with the plan.
Cl earance appears adequate for hot operations.
(Closed) Unresolved Item (320/77-42-10): Tempor:ry change notice (TCN) control.
Controls have been established to ensure removal of cancelled TCN's from control room procedures.
The inspector reviewed the TCH log and determined that selected cancelled TCN's had been removed from the applicable procedures.
(Closed) Unresolved Item (320/77-42-11):
Equipment tagout index.
Licensee representatives stated that an index of active equipment tagouts was not currently planned. The status of active tagouts can be determined by review of the active and cleared tagout requests and associated switching orders. The inspector determined that the licensee's controls for tagged equipment were acceptable, as discussed in paragraph 4.b of this report, and had no further questions concerning this matter.
(Closed) Unresolved Item (320/78-03-01): TP 600/4 evaluation. The licensee has at:epted 1 cycle out of the 40 for the high pressure injection transient, which resulted during performance of TP 600/4.
The transient at 85"F injection water temperature was less severe than the analyzed transient with 60*F injection water.
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(Closed) Unresolved Item (320/78-17-01):
Control of caution tags.
SAP 1037, " Control of Caution Tags," has been fully implemented.
The inspector verified that the use of CAUTION tags and D0-NOT-OPERATE tags was in conformance with the requirements of SAP 1037.
(Closed) Inspector Followup Item (320/78-17-02): Timely completion of PORC action items.
Peasures had been established to ensure that PORC action items are completed as scheduled and to approve extended completion due h tes, when necessary. Additionally, FORC action items 2-78-005, 2-78-012, 2-78-014, 2-78-009, and 2-78-C10 have been satis-factorily completed. The inspectnr had no further questions regarding this item.
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(0 pen) Inspector Followup Item (320/78-17-03):
Resolution of PORC Action Items regarding IE Circulars.
PORC Action Items (PAI) 2-78-023 and 2-78-020, concerning PORC review of IE Circulars 77-16 and 78-02, have been satisfactorily completed.
PAI 2-78-022 con-cerning IE Circular 77-14 remains outstanding for PORC revicw.
Licensee determination that contaminated water systems are adequately separated from noncontaminated plant systems will be reviewed during a subsequent inspection.
3.
Main Steam Relief Valve /Pipino Modifications a.
General The main steam line safety relief valves were determinea to have excessive blowdown characteristics, as described in Licensee Event Reports 78-33 and 78-34.
Subsequent modifications to the safety relief valves, MSRIA through MSR6A and MSRlB through MSR6B, did not correct the inability to obtain repro-ducible lift pressure, reset pressure or blow-down setpoints.
The original valves were a prototype dual exhaust design, manufactured by the J. E. Loaergan Company. The twelve valves have been removed and are being replaced with twenty, single exhaust, 6R10 Dresser Relief Valves (Reference:
Burns and Roe Drawing SK-A161).
The documentation used as the basis for acceptance criteria for the main steam valve / piping modification included:
FSAR Section 10, Steam Generator Relief Valves; TMI-2 Technical Specifications; 10 CFR 50.59(a); Burns and Roe (B&R) Field Change Request (FCR) 2520.1, Revision 2, and FOR 2520.2, Revision 2; ASME Section III, Class II,Section V and IX; ASTM; and ANSI B31.7.
The inspector reviewed QC procedures and records with respect to material receipt, storage, and handling; welding; post weld heat treatment; nondestructive exanination; planned testing; and mechanical pipe arrestors.
b.
Material Receipt, Storage, and Hanoling The QC program contains appropriate procedures for materials checks and record retention. Thr.se procedures include QC-2-2,
" Receiving Inspection," Revisior, 7, Field Change #0C-205; QC-3-2, "Storag6 Control," Revision 3; and QC-6-2, " Records and k ~
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Filing System," Revision 7, Field Change #QC-266.
The inspector reviewed the records for the long neck flanges which included Mill Test Report - Coffer Corporation #12118.
A material chemical and physical check were made by the inspector.
The records for the split plate assemblies, Purchase Order (PO)
Nn. 7064-65-11. and records for the flexible gaskets, P0 No.
7064-65-4, were reviewed.
Conformation Certificates for Material Shipped, Order 59703, Flexitallic Gasket Company, confim leachable chloride to be less than 200 ppm as specified.
The inspector reviewed the OA data package and documentation indicating QA participation in the witnessing of vendor testing of the new main steam relief valves.
The documents reviewed included TMI-2 Interoffice Memorandums, dated July 13 and July 19, 1978.
The licensee witnessing inspection, Trip Report dated July ll,1978, addresses the Confirmation of B&R Design Specification 2555-147, Main Steam Safety Valves. The inspector reviewed Burns and Roe TWX to Dresser Valves, Inc., dated July 11, 1978, which also addresses the certification by B&R that the Sargent and Lundy Design Specification, F-2761 and L-2761 meet or exceed the requirements of B&R Specification 2555-147.
The inspector determined that documentation available attests to an active program to assure receipt of acceptable valves.
No items of noncompliance were identified.
c.
Welding The main steam safety relief valve piping modification was in The penetrations to receive the long neck flanges progress.
had been finalized...The: fit-up and welding of the long neck flanges and the split plate supports was in progress.
The inspector witnessed a part of the welding being perfomed on location 26B, 22B, and 25B in accordance with Crouse Company Incorporated Welding Sequence, dated July 1, 1978.
visually examined the partially completed welds, per Weld Pro-The inspecto cedure Specification GTA-SMA-1,1-P-102, including checks for slag, dirt, and crater indications. The weld at 27B, which has been completed, was inspected and appeared to be smooth
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and clear of visual defects.
for contour and smoothness.
The inside diameter was inspected
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9 The new weld rod ordered for the modification was checked for receipt and storage.
The rods in use were inspected for dis-
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bursing and handling controls.
At the receiving station the E-7018 filler rods were in hennatically sealed containers and tagged with QC release for construction, Tag. No. C-879. The records for this order (P0 36590-8798) were inspected for Certified Materials Test Reports (Chemtron No. 4029 and 4034) and receiving checklist.
The inspector checked the weld rod disbursing station for control of weld rod issuance, weld rod return, and oven weld rod storage.
The weld rod was being issued as documented on the Request for Welding Electrodes (GPU fonn).
The rebake oven was checked and did not contain any electredes. The Mechanical Construction Procedure for " Control of Weld Rod and Consumable Insert,"
MCP 2-2, Revision 12, requires that weld rods, if not issued, should be placed in holding /st rage ovens and maintained at 250 F + 25 F.
The inspector found the low hydrogen electrode storage oven temperature indication at 190 F, which was below the required holding temperature, at approximately 8:00 a.m.,
on July 20, 1978. This constitutes an infraction level item of noncompliance (320/78-24-01).
The inspector checked the welders performance and procedures qualification records for the three in-process welds noted above. The records of welders identified as F-5, F-9, and F-21 were reviewed and found acceptable.
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Post Weld Heat Treatment
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The inspector reviewed the draft post weld heat treatment pro-cedure for FCR 2520.1, " Heat Tracing," Revision 0, dated July 18, 1978, to verify that it complies with the USAS B31.7 Code requirements.
Paragraph W.1.5.1.b does not fully comply, in that the heating and cooling rates above 600'F are greater than those allowed by the USAS B31.7 Code, paragraph 1-731.3.3.
This item is considered unresolved pending(a change in the procedure and subsequent review by NRC:RI 320/78-24-02).
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Nondestructive Examinations e.
The licensee is performing radiography on the long neck flang welds in accordance with Conam Nondestructive Testing Procedure XR-1-NP.
The radiography is being performed using an Iridium-192 gamma source, 87 Ci s+.rength.
The procedure was reviewed and found to be acceptable and in accordance with ANSI B31.7 1969 and the 1970 addenda.
No items of noncompliance were identified, f.
Planned Testino The licensee plans to conduct a hydrostatic test of the completed modification and a test of the main steam relief valves using a hydraulic ram followed by an actual lift.
TP 271.4 and TP 209, are currently being finalized.The two procedures, No items of noncompliance were identified.
g.
Mechanical Pipe Arrestors For the relief valve / piping modification, mechanical pipe arrestors MSH-284-5 (two with this number), MSH-280-S, and MSH-292-S appear to be stored, or partially engaged in a manner which makes them subject to damage.
The licensee plans to modify pipe restraints MSH-230-S and MSH-284-S (Reference:
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FCR No. 2520.1, Revision 1).
280 and 284 to be removed to a new location.This FCR also requires unit Corrective action work on the main steam relief valve / piping modificatio licensee stated that the suspect units will be checked forThe proper functioning prior to or during the test program following the completion of the modification.
questions at this time.
The inspector had na further No ite:ns of noncompliance were identified.
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Review of Plant Operations Shift Loas and Goeratino Records a.
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The inspector reviewed the following logs and records:
Shift Foreman Log, Control Room Log Book, Control Room
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Tour Readings, Primary Atxiliary Operator's =
Waste 3isposal Panels, Secondary Auxiliary Operator's Log Sheets, and Auxiliary Operator Log Sheets-Out-Building Tour; dated May 1 - July 31, 1978.
Shitt and Daily Checks; dated May 1 - July 25,1978.
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Jumper, Lifted Lead, and Mechanical Modific
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1978.
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Fire System Removal from Service Motification Log; entries I
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made during February 8 - July 31,1978.
Applications for Apparatus to be Taken Out of Service;
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those active on August 1, 1978, and those cleared dated July 17-31, 1978.
s Do Not Operate Tag Log; entries made during May 6 - July 31
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Transient Cycle Log Book; entries made during May 6 - July
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and updated entries for the period February 8 -
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Unit 2 Operations Department Memos 2-78-9 through 2-78-15
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The logs and records were reviewed to verify the following items
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Logkeeping practices and log book reviews are conducted
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in accordance with established administrative controls Log entries involving abnormal conditions are sufficiently
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detailed.
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Operating orders do not conflict with Technical Specifica-
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tions (TSs).
Jumper log and tagging log entries do not conflict with
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TSs.
Jumper / lifted lead / mechanical modification and tagging
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operations are conducted in conformance with established administrative controls.
Problem identification reports confirm compliance with TS
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reporting and LCO requirements.
Acceptance criteria for the above review included inspector judgement and requirements of applicable Technical Specifications and the following procedures.
Station Administrative Procedure (SAP) 1002, " Rules for
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the Protection of Employees Working on Electrical and Mechanical Apparatus," Revision 12.
SAP 1010. " Technical Specification Surveillance Program,"
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Revision 12 TCN 2-78-507.
SAP 1011. " Controlled Key Locker Control," Revision 16.
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SAP 1012. " Shift Relief and Log Entries," Revision 8.
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SAP 1013, " Bypass of Safety Functions and Jumper Control,"
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Revision 7.
SAP 1016. " Operations Surveillance Program," Revision 12.
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SAP 1033, " Operating Memos and Standing Orders," Original.
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SAP 1037, " Control of Caution Tags," Original.
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The inspector noted that the Transient Cycle Log Book had been upda'.ed and the administration of controls for lifted leads and jumpers had improved since the last inspection in this area.
The inspector's findings regarding shift logs end operating rerords were acceptable.
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b.
Plant Tour On August 2-3, 1978, the inspector conducted a tour of the following accessible plant areas.
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Auxiliary Building Turbine Building
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Fuel Handling Building Control Room
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Switchgear Rooms
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Inverter and Battery Rooms
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Diesel Rooms
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Chemical Addition Room
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Makeup Pump Rooms
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Building Spray Pump and Decay Heat Pump Vaults Evaporator Room
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The following observations / discussions / determinations were made.
Control Room and local monitoring instrumentation for
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various components and parameters was observed, including diesel fuel oil levels, control rod positions, and RCS pressure and temperature.
Radiation controls established by the licensee, including
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the posting of radiation and high radiation areas, the condition of step-off pads, and the disposal of protective clothing, were observed.
Radiation work pennits used for entry to radiation and controlled areas were reviewed.
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Plant housekeeping, including general cleanliness condi-tions and storage of materials and components to prevent
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safety and fire hazards, was observed.
Systems and equipment in all areas toured were observed for the existence of fluid leaks and abnormal piping
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vibrations.
Selected piping snubbers / restraints were observed for proper fluid level and condition / proper hanger settings.
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The indicated positions of electrical power supply breakers and selected control board equipment start switches and
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remote-operated valves and the actual positions of selected l
manual-operated valves were observed.
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Selected equipment lockout tags, caution tags, and Do-Not-Operate tags were observed for proper posting and the
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tagged equipment was observed for proper positioning, where applicable.
Selected jumper and lifted lead markers were observed
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for proper identification and the effected wiring changes were observed for proper completion.
The Control Board was observed for annunciators that
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normally should not be lighted during the existing plant
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conditions. The reasons for the annunciators were discussed with control room operators.
The licensee's policy and practice regarding plant tours
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was reviewed.
Control Room manning was observed on several occasions
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during the inspection.
Acceptance criteria for the above items included inspector -
judgement and requirements of 10 CFR 50.54(k), Regulatory Guide 1.114, applicable Technical Specifications, and the following procedures.
SAP 1002, " Rules for the Prctection of Employees Working
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on Electrical and Mechanical Apparatus," Revision 12.
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SAP 1003, " Radiation Protection Manual," Revision 12.
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SAP 100a, " Good Housekeeping," Revision 3.
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SAP i009, " Station Organization and Chain of Co:=and,"
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Revision 3.
SAP 1028, " Operator at the Controls," Original.
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SAP 1037, " Control of Caution Tags," Original.
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The inspector's finding regarding the plant tours were accept-able, except as noted below:
The inspector noted that general cleanliness conditions
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in the auxiliary building upper levels had improved since tre last inspr.ction in this area.
However, cleanliness and material storage conditions in the auxiliary building basecent, including the BS and DH vaults, and in the reacto.- building require correction.
Licensee representa-tives we e aware of the degraced conc'itions in these areas and nave st..keduled appropriate cleamo and removal of excess material prior to heatup or resuming power operation.
The inspector had no further questions concerning this matter at this time.
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During observation of control room and local annunciators,
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the inspector noted an inconsistency in diesel generator alarms.
The Low Lube Oil Day Tank Level Alarm was lighted on both local annunciator panels, but on only cne control
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room panel.
Licensee representatives stated that the apparently out-of-service alann would be investigated.
The licensee's investigation of this alarm is considered an unresolved item (320/78-24-03).
5.
Nonroutine Event Review
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The inspector reviewed the licensee's system for identification, review, reporting, and followup of nonroutine events. The review was performed to determine that responsibilities have been assigned for the items listed below:
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Prompt review and evaluation of off-normal operating events
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to assure identification of safety related events.
Prompt review of planned and unplanned maintenance and testing
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activities to assure identification of violations of Technical Specification LCO requirements.
Reporting safety related operating events internally and to
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the NRC.
Assuring cc.apletion of corrective actions relating to safety
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related operating events.
Administrative controls for reporting nonroutine events are described in GP 4703.
There is no administrative procedure which specifies responsibilities for nonroutine event identification, review, and followup.
Licensee representatives stated that these functions are inheren*.ly performed by facility management, PORC members, and licensed operators, based on their knowledge of Technical Specifi-cations reporting requirements.
Nonroutine events are 'dentified during shift foreman review of Control Room logs ad c -
eted surveillance procedures, PC.lC review of completei nintenance activ-ities, and departmental supervisory review of rou une operations.
Reportable matters are promptly referred to facility management and PORC for review and evaluation. Applicable corrective actions are tracked for completion by designation as PORC Action Items.
The inspector noted that the licensee's fenctions associated with non-routine events have been acceptable since license issuance and had no further questicns concerning this matter.
6.
In-Off_ ice Review of Licensee Event Reports (LER's)
The LER's listed below were reviewed in the Region I office promptly following receipt to verify that details of the event were clearly reported including the accuracy of the description of cause and the adequacy of corrective action. The LER's were also reviewed to deter-mine whether further information was required from the licensee, whether generic implications ware involved, whether the event should
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be classified as an Abnormal Occurrence, and whether the event warranted onsite followup.
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The following LER's were reviewed:
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LER 78-24/3L, dated May 4,1978; NS-V83B failed to open during
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surveillance testing due to malfunction of solenoid-operated pilot valve.
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LER 78-26/3L, dated May 2,1978; RCS wide range pressure trans-mitter RC-3A-PT4 failed due to meisture induced short circuit
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in.the transmitter terminal box.
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LER 78-27/1T, dated May 2,1978; Error in small break LOCA safety analysis.
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LER 78-28/3L, dated May 3,1978; DC-V103 failed to close during SFAS surveillance testing due to a failed motor on the valve operator.
LER 78-29/3L, dated May 10, 1978; Ventilation damper D-4098
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failed to close during surveillance testing due to improperly adjusted linkage.
LER 78-30/3L, cated May 17, 1978; RPS Channel C tripped on
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Hi Flux due to damage of NI-7 during initial installation.
LER 78-31/3L, dated May 18,1978; CA-V3 failed to completely
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close during SFAS surveillance testing due to incorrect torque switch setting.
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LER 78-33/lT, dated May 8,1978; Reactor trip followed by RCS depressurization and sodium hydroxide injection, due to steam generatcr safety valves not properly reseating.
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LER 78-34/lT, dated May 8,1978; Degradation of main steam safety valve discharge piping.
- - - ' LER 78-35/lT, ilated May 9,1978; Unit aur.iliary transformers incapable of carrying full load and ESF auxiliaries durino periods of perk demand.
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LER 78-36/lT, dated May 18, 1978; Error in uncertainties applied to incore detector measurements of imbalance and quadrant power til t.
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- LER 78-37/3L, dated May 25, 1978; Emergency Diesel Generator
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"B" failed surveillance test and tri pressure due to undetennined cause. pped on high crankcase LER 78-38/3L, dated June 12, 1973; While performing monthly
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surveillance, the setting of BS-FS-3260 was found to be 0.02 psig higher than TS limit due to instrument drift.
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LER 78-39/3L, dated June 15, 1978; Emergency Diesel Generator
"B" failed to start during surveillance testing due to failure of the vertical shaf t between the upper and lower crank shafts, caused by improper caterial.
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LER 78-40/3L, dated June 15, 1978; Chiller AH-C-88 failed to had a rough edge on its stem. operate during surveillance testing du
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LER 78-41/3L, dated June 15, 1978; Emergency Diesel Generator due to partially plugged neifice plate to the crank ejector.
LER 78-42/3L, dated July 14, 1978;
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the Damper 4092c accumulator pressure could not be maintain within 10 psi of the initial pressure due to improper location i
of the associated 3-way valve.
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LER 78-43/3L, dated July 10, 1978; Deficient floor fire barrier
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make the seal. penetration seal due to improperly cured foam material used to
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LER 78-44/3L, dated July 24, 1978; for the "A" Diesel Ger.erator was not closed when the unit wasM placed in emergency stundby, due to a procedure ir. adequacy.
The above LER's were closed, based on satisfactory review in the Region I office, except those LER's selected for onsite followup
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Onsite Licensee Event Followup For those LER's selected for or2ite followup (denoted in Paragraph 5), the inspector verified that the reporting requirements of Technical Specifications and GP 4703 (Original) had been met, that apprcpriate corrective action had been taken, that the event was reviewed by the licensee as required by Technical Specifications, and that continued operation of the facility was conducted in con-formance with Technical Specification limits.
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The inspector's 'indings regarding these licensee events were acceptable, unless otherwise noted below.
Corrective measures 6ssociated with LER's 78-33/lT and 78-34/IT
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are being tracked for completion by PORC Action Item 2-78-025.
The ECCS actuation of April 23, 1978, and the licensee's evalua-tion of the transient and designation of corrective actions were reviewed during a previous inspection, as described in OIE Iispection Report 50-320/78-17, paragraph 8.
Modificaticns of the main steam safety relief valves and piping, to prevent recurrence of excessive valve blowdown, are described in para-graph 3 of this report. The above LER's stated that prior to criticality the relief valves will be tested for proper lift pressure and also to insure that blowdown is not excessive.
Complet^on of satisfactory relief valve testing prior to criti-cality is an unresolved item (320/78-24-04).
The i tspector noted that some of the LER's reviewed onsite
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centa;ned coding errors or narrative omissicns. Specific examples of these reporting inadequacies and the requirements of NUREG-0161, " Instructions for Preparation of Date Entry Sheets for Licensee Event Report (LER) File," were discussed with licensee representatives. Tlic inspector stated that updated reports were not required to correct the identified errors.
Licensee representatives stated that appropriate action would be taken to ensure that future LER forms are complete and accurate. The inspector had no further questions concerning
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this item.
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LER 78-44/3L contained inadequate narrative descriptions of
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the event and the cause.
/.lictnsee representative stated that an update LER would be submitted to correct these reporting discrepancies.
Licensee submission of an update LER and com-pletion of personnel instruction to ensure that procer diesel generator electrical lineup is established and maintaineo is an unresolved item (320/78-24-05).
8.
IE Bulletin and Circular Fol'lowuo The inspector reviewed the licensee's followup actions regarding the IE Bulletins and Circulars listed below.
IEB 77-07, " Containment Electrical Penetration Assemblies at
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Nuclear Power Plants Under Construction," dated December 19, 1977.
IEB 78-01, "Flamable Contact-Arm Retainers in General Electric
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(GE) CR120A Relays," dated January 16, 1978.
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IEB 78-02, " Terminal Block Qualification,". dated January 30, 1978.
1EB 78-04, " Environmental Qualification of Certain Stem Mcunted
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Limit Switches Inside Reactor Containment," dated February 21, 1978.
. IEB 78-05, " Malfunctioning c? Circuit Breaker Auxiliary Contact
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Mecha.nsm - General Electric Model CR105X, dated April 14, 1978.
IEB 78-06, " Defer.tive Cutler-Hancer Type M Relays with DC
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Coils," dated FDy 31, 1978.
IEC 78-04, " Installation Error That Could Prevent Closing of
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Fire Doors," oated May 18, 1978.
IEC 78-05, " Inadvertent Safety Injection During Cooldown,"
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dated May 26, 1978.
IEC 78-07, " Damaged Components on a Bergen-Patterson Series
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25000 Hydraulic Test Stand," dateo May 31, i978.
This review included discussions with licensee personnel, review of selected facility records, and observation of selected facility ecuipment and ccmponents.
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With respect to the above Bulletins, the inspector verified that licensee manaegement forwarded ccpiE3 of the bulletin response to appropriate c onsite management representatives, that infor nation and corre:tive ac-: tion discussed in the reply was accurate and effected as described-, and that the reply was submitted within the time period described in. the bulletins.
With respect to the above Circulars, the inspector verified that the circular was received by aporopr u te licensee management, a review for a plicability was perforred, and that action taken or planned is ac:propriate.
Acceptance c:--iteria for the above review included inspector judgement and requiremeents of applicable Technical Specifications and facility procedures.
Licensee folT-twup to the above Bulletins and Circulars was acceptable, unless other. rise noted below.
IEB 78-C 1 concerned fire damage of several GE CR120A relays
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which oc-urred at another facility.
The fire was attributed to an overheated relay coil that ignited the relay's plastic contact--arm retainer.
The corrective action recommended by GE was t::o replace the flamable Celcon retainers of designated relays w-ith improved self-extinguhhing flame resistant Valoz retainer %
t The licernsee has determined that many of the GE CR120A and
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CR122. relays installed
'n safety related and balance of plant
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equipmer.t have the Celcc contact-ann retainers. A list of all such relays has been compiled, and necessary replacement Valoz-type retainer 3 have been ordered.
Burns and Roe ECM S-5989 has been approved to perform retainer replacement.
Licensee completion of ECH S-5989 upon receipt of replacement materials is considered an unresolved item (320/78-24-06).
IEB 78-05 concerned a problem encountereo with the operation
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of a GE Model CR105X auxiliary contact mechanism at another facility.
An auxiliary contact had failed in the closed
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position due to binding of the plunger arm caused by burrs and nicks on its surface.
The corrective action recomended by GE was to replace the plunger ann of affected relays.
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see has determined that 32 GE NEMA size 1 contactors
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are inpalled in safety related systems and 94 such contactors in balance of plant equipment.
Each of these contactors are usec;;._ _, three model CR 105X100P auxilirry contact mechanisms.
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o b O ng problems have been encountere 1 with these as of has c However, the licensee plans to replace the potentially
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g5 c rechanisms in the appropriate equipment as well as in bindir -
- es inventory.
MEC letter to NRC Region I serial GQL the s '
ted May 20, 1978, stated that changeout will be completed
as possible but nct later than the end of the first
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as y scheduled refueling outage. The inspector determined
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ecu ssary replacement parts have net yet been ordered, tdt '~.c ::u hment of the changeout has not yet been scheduled or BjC_
by an ECM.
Since implementation of the changeout rp_7.iat any long-tem deferrals in changeout should be be fully completed for an extended period, the inspector
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The basis for deferral
"Ctectn -dly supported and justified.
-include a revita of the function and safety significance
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S affected auxiliary contact mechanism and a review of 0f p - checks or component surveillance that is perfomed to ro'_
-e-.- ate continueo equipment operability until changeout
.p- -l e ted.
Licensee completion of actions concerning IEB g
g378,g s considered an unresolved item (320/78-24-07).
-:eview of Measures Established to Imolement 10 CFR Part 21 9.
O utr g d on procedures listed belr ere reviewed in the Region I office-gp cc75, Revision 0, Change 1 (Novemb.
18,1977)," Reporting g ref._-cts and Noncompliance as Required by 10 CFR 21."
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GP 0029, Revision 3 (January 2,1978), " Generation Division Honconformances."
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GP 0063, Revision 0, Changa 3 (March 13,1978), " Record Control."
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gp
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Revision 1 Change 3 (April 10,1978), ' Procurement
,i. Control."
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gp 1011, Revision 1, Change 2 (October 18.1977), " Preparation, Changing, and Issuance of Specifications and Bills.of Material."
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GP 1024, Revision. 3, Change 2 (February 28,1978), "Identifi-
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cation and Evaluation of Nonconfoming Materials, Parts, and
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Components."
GP 4005, Revision 2, Change 3 (February 15, 1978), " Review of
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GP 4012, Revision 4, Change 2 (May 8,1978), "Nonconfomance
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Reports, and stop Werk Orders."
GP 4414. Revision 0 (February 14,1978), " Receipt Deficiency
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Reporting."
GP 4705, Revision 0 (December 3, 1977), " Licensing Reviews
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for Reportability."
The procedures were reviewed to verify that the procedures or controls listed below have been established and are adequate to assure imple-mentation of 10 CFR Part 21 requirements.
Controls or procedures for posting (21.6).
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Procedures for evaluating deviations or infoming the licensee i
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or purchaser of deviations (21.21(a)).
Procedures for infoming a director or responsible officer of:
1) deviations evaluated to be a defect, or 2) failures to comply
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relating to a substantiated safety hazard (21.21(a)).
Controls or procedures which will assure that a director or responsible officer will infom the Comission as required
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when receiving information of a defect or reportable failure to comply (21.21(b)).
Controls or procedures to assure that each procurement document for a facility or basic component, when applicable, specifies
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that provisions of 10 CFR Part 21 apply (21.31).
Controls or procedures to assure licensee maintenance of
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records (21.51(a)).
Controls or procedures to assure the preparation and appropriate
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disposition of records (21.51(b)).
No items of noncompliance were identified.
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10.
In-Off-C__ _
f Peri dic and Soecial Reports Review The pergj-and special reports listed below were reviewed in the
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Re9 iice to verify that the report included information be reported and that test results and/or supporting in-e9-iscussed in the report were consistent with design pre-format.--
dictic
- d performance specifications, as applicable.
The reports
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eviewed ta u cartain whether planned corrective action were a tih of identified problems, where applicable
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.my information contained in the report and to
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should
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The folE '#
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j + fort, dated March 13, 1978.
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Ma - - T>p e ra, a Report, dated April 13, 1978.
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gg Sperating Report, dated May 15, 1978.
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~~jerating Report, dated June 15, 1978.
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Jure Berating Report, dated July 13, 1978.
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The fol Wg M 2 special reports were reviewed.
Re;crt of ECCS Actuation of March 29, 1978, dated June 27, 1978.
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Report of ECCS Actuation of April 23, 1978, dated July 24, 1978.
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The above reports were closed based on satisfactory review at the Region I office.
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11. Unresolved Items i
Unresolved items are matters about which more infonnation is required in order to ascertain whether they are acceptable items, items of
noncompliance, or deviations.
the inspection are discussed in Paragraphs 3.d 4.b, 7, and 8. Unresolved items disclose l
12.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the ir.spection on August 3,1978.
The in-spector sumarized the purpose and secpe of the inspection and the findings.
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