IR 05000286/1982005
| ML20052G265 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/26/1982 |
| From: | Baunack W, Grey E, Kenny T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20052G262 | List: |
| References | |
| 50-286-82-05, 50-286-82-5, NUDOCS 8205140465 | |
| Download: ML20052G265 (13) | |
Text
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Enclosure:
tiuclear Regulatory Counission Inspection Report Humber 50-286/82-05 ..
REGION I== 820327 Report No. 50-286/82-05 Docket No. 50-286 License No. DPR-64 Priority Category C -- Licensee: Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 Facility Name: Indian Point Nuclear Generating Station, Unit 3-Inspection at: Buchanan, New York Inspection conducted: March 16, 1982 to April 15, 1982 Inspectors: A b T. J. Kenny, Resident Inspe or date ' ' [[ V/2.6/6L-E. H. Grey, ReactgVInspector date ihl- ) % su' W. Ba~unack, Acting Chief, Indian Point / ' date - - Resident Section, Division of Project ^ and Resident Programs Inspection Sumary: Inspections on March 16, 1982 to April 15,1982 (Inspection Report 50-286/82-05) ! Areas Inspected: Routine onsite regular and backshift inspections,of plant operations including shift logs and records; licensee action on previous in- - spection findings; plant tour; surveillance; maintenance; followup on IE circulars ! ! and IE bulletins; steam generator tube leaks; and steam generator closure seam indications and program. The inspection involved 139 hears by the resident and regional inspectors.
Results: Of the nine areas inspected, no violations were identified.
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. . DETAILS , 1.
Persons Contacted M. Albright, Instrument and Control Superintendent J. Boardnan, Inservice Inspection Engineer J. Brons, Resident Manager Z. Dicic, Director Mechanical Design and Analysis J. Dube, Security and Safety Supervisor , L. Gwynn, Quality Assurance Engineer ~ D. Halama, Q. A. Superintendent W. Hamlin, Assistant to the Resident Manager W. Josiger, Superintendent of Power J. Perrotta, Radiological and Environmental Services Superintendent S. Munoz, Technical Services Supervisor ' ' W. Spataro, Senior Metallurgist E. Tagliamonti, Operations Superintendent J. Vignola, Maintenance Superintendent The inspector also interviewed and observed other licensee employees in-cluding members of the operations, health physics, technical services, maintenance, and security staffs.
2.
Licensee Actions on Previous Inspection Findings (Closed) InspectorFollowItem(50-286/79-16-02): Check on the progress of pressure suppression for the charging pumps. The inspector reviewed and verified Modification 79-3-021 CVCS which added suction pulsation dampers to all charging pumps.
(Closed) Inspector Follow Item (50-286/79-1S-03): Check on the progress of the water manufacturing plant. The inspector verified that the water manufacturing plant is currently processing 200 gal / min.
(Closed) Infraction (50-286/79-23-06): Inadvertent containment spray.
The inspector reviewed the licensee's letter dated April 7,1980, and verified that corrective action has been taken. The inspector also witnessed portions of spray pump testing during this refueling period and found the test satisfactory.
(Cicsed) Unresolved Item (50-286/79-29-01): Incorporation of El-6009 (Con Ed Electrical Manual) into PASHY Maintenance Program. The licensee plans to incorporate its own manual in the future, but currently has incorporated 51-6009 into the maintenance program. The inspector reviewed two Modifications; (1) 82-03-03 EL " Audibility Improvements to Party Page System"; (2) 82-03-049 COMP " Emergency Facilities Data Acquisition and Display System Installation Display," and verified reference to El-6009.
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(Closed) UnresolvedItem(50-286/79-29-04): 3PC-RI(c) - Final Review of Corrective Action Regarding Procedure Acceptance Criteria. See Item 50-286/79-27-07.
(Closed) Inspector Follow Item (50-286/79-29-05) 3PCR13 - Review Maintenance on R17B and R19 to Assure Proper Operation in the Test Position. See Item 50-286/79-27-07.
(Closed) Unresolved Item (50-286/79-29-06) 3PCR4 - Review Calibration Data ' and Assure the Method for Detennination of Lead-Lag Time Correct. See Item 50-286/79-27-07.
' (Closed) Infraction (50-286/79-29-07): This item of noncompliance was issued because of the collective previous three items. The item was the failure of the licensee to review the calibration data, and actions taken, at the conclusion of the tests performed. The inspector reviewed and verified the corrective actions listed in the licensee's letter of June 13, 1980. The inspector also reviewed: 3PC-R18 Rev. 2 of October 29, 1980; - 3PC-R1(C) Rev. 2 of October 7,1980; - 3PC-R13 Rev. 2 of February 20, 1980; - 3PC-R4 Rev. 2 of October 14, 1980; and, - verified that the as-found data and corrective actions were reviewed by the licensee in accordance with procedures.
(Closed) Infraction (50-236/79-29-08): - Failure to properly complete the containment inspection as per Technical Specification 4.4.8.
The inspector reviewed and verified the corrective actions of the licensee's letter of June 13, 1980. Theinspectoralsoreviewed3PT-A3(ContainmentInspection) performed September 10, 1981, and verified that the concerns of Technical Specification 4.4.8 were accomplished.
(Closed) Violation (50-286/82-01-01): Failure to perform a Safety Evalua-tion on Isolation Valve Seal Water System Modification. The inspector has reviewed and verified the actions taken by the licensee in their letter dated March 26, 1982.
3.
Plant Tour A.
Normal and backshift inspections were conducted during routine entries into the protected area of the plant, including the control room PAB, fuel building, and containment. During the inspection activities, discussions were held with operators, technicians (HP & I&C), mechanics, foremen, supervisors, and plant management. The purpose of the inspection was to affirm the licensee's comitments and compliance with 10 CFR, Technical Specifications, and Adninistrative i Prccedures.
Particular attention was directed in the following areas:
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, Alarmed control room annunciators, assuring that the operators - understood the reason and the importance for each, and that correc-tive action was being taken for each.
Control room, shift supervisor, senior operator and watch per- - sonnel logs, assuring that trends, out-of-specification read-ings and anomolities: if any, were being challenged.
That panel board displays and system lineups were in compliance - with the licensee's procedures for safe operation.
That pressure and temperature relationships in the containment, - primary and secondary systems were in compliance with operating procedures.
That protected area access controls were in conformance with - the security plan, including sufficient guards to perform duties, and that selected gates and doors were closed and locked.
That selected ESF trains were operable in accordance with - Technical Specifications and plant procedures.
B.
The inspector conducted biweekly inspections in the areas mentioned in paragraph "A" above, observing, where possible: Surveillance being conducted on plant parameters and equipment - involving safety. Surveillance results are documented in para-graph 4 of this report; - Ongoing ESF maintenance being conducted to assure compliance with licensee's procedures.
Maintenance results are documented in paragraph 5 of this report; Selected liquid and gaseous samples to verify conformance with - regulatory requirements prior to release; Boric acid samples to confirm proper boric acid level for plant - l operation; ! Visual observations of operating equipment and piping systens l - to ascertain if any leakage paths, vibration, unlocked normally l l locked valves, obstructions to valve operators, and loose sup-ports existed; i I l - ! l l L
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Shift turnovers including a review of shift turnover sheet; and, - In general, observation of the following for compliance with - regulatory requirements: 1) Proper completion and use of selected radiation work permits;
2) Proper use of protective clothing and respirators; 3) Proper personnel monitoring practices (wearing of badges and use of monitoring equipment); 4) Ignition scurces and flammable materials are being con- ^' i trolled to assure that they are in accordance with 11-censee procedures; 5) Equipment tagouts for conformance with controls for re-
moval of equipment from service; and, 6) Plant housekeeping cleanliness practices for conformance with approved licensee programs.
C.
During the inspection, the inspector reviewed the following procedures, documents, or tests: - Radioactive Waste Release Permit 625 for #34 LGDT;(gaseous)
Various shift turnover checklists - Security Station Logs - Jumper Log - COL-RM-1 - Radiation Monitoring and Protection System - AP-10.1 - Operating Orders and Control of Stop Tags and - "Do Not Operate" Tags Tag-outs 500153 - 500177 500163 #34 Fan Cooler Unit No violations were identified.
4.
Surveillance A.
The inspector o'oserved portions of four surveillance activities being conducted on safety-related equipment to ascertain the following: That test instrumentation was properly calibrated; - That the redundant system or component was operable; - . That properly approved procedures were used by qualified - personnel; and, That the acceptance criteria was met.
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Tests observed: 3PT-SA11 OPS Analog-3PT-M14A SI Logic "A" 3PT-R53 Containment Sump Test 3PC-R17 Calibration of Pressure Transmitter P937D (Accumulator) 3PC-R1(C)- R.C. Loop Wide Range Cold Leg Calibration No violations were identified.
B.
The inspector conducted an indepth review of surveillance activities to ascertain the following: That the conditions listed in "A" above were met; - That the test data was accurate and complete; - r That proper reviews, by the licensee, had been conducted; - That the results of the tests met Technical Specification - requirements; and, - That the testing was done within the required surveillance schedule.
Tests reviewed: 3PT-R35 WCCPRack#10(B&CTesting) 3PT-M15 Main Turbine Stop and Control Valve Test 3PT-Q20 Surveillance and Inservice Inspection Test Auxiliary Boiler Feed Valve Testing Recombined Functional Test i 3PT-R12 H2 3PT-CS13 Inservice Inspection Test RHR Mini Flow Valves 743 and 1870 Operability 3PT-CS9 Safety Injection to the Hot Leg (Valve 856B and 856G) 3PT-R10A Residual Heat Removal System Leakage Test No violations were identified.
5.
Maintenance A.
The inspector selected maintenance activities being conducted on ESF equipment to ascertain that redundant trains were in service, and that approved procedures and qualified personnel were ' conducting, the maintenance.
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B.
The inspector observed portions of maintenance activities listed below to ascertain the following: The activities did not violate a limiting condition'for' - operation; That redundant components were operable;^ - That equipment was tagged out in accordance with licensee' approved - procedures; ' Tnat approved procedures, adequate to control the activity, were - 1aing used by qualified technicians; That Q/C hold points were observed, and that materials were pro- - perly certified; That radiological controls were proper and in accordance with - licensee approved radiation exposure authorization's; and, ' - That the equipment was properly tested prior to return to service.
1) Replacement of MS55 Valves (Bypass Around Main Steam) Documents Reviewed: Modification Procedure 81-03-040 MS - Maintenance Request 2612 - Drawing fMSK-007 - Weld Requisition Fonn 12806 - - QA Procedure 7.3 AP-33 Weld Rod Control Procedure - - Qualifications for Welder D-1 - Purchase Orders 82-IP-0702 - Schedule 80 Pipe 81-IP-0067 - Con Valve - Certification Papers D-191 - Schedule 80 Pipe C-543 - Con Valve 2) Main Feed Regulator Overhaul Documents Reviewed: - Procedure 3-CM-GEN-6 - Copes Vulcan Air-Operated Control Valve Overhaul Maintenance Request 2808 - No violations were identified.
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6.
Followup on IE Circulars The inspector reviewed the following IE Circulars. For each circular reviewed, the inspector ascertained that: '
The circular was received by the licensee's management.
- The circular was reviewed for applicability.
- ~ For each circular, if it is applicable to the facility. -the - appropriate corrective actions have been taken or are scheduled to be taken.
(Closed) 77-CI-15 - Degradation of Fuel Oil Flow to Emergency Diesel . Generator. By review of PORC mir.utes and the Emergency Diesel Generator Fuel Oil System, the inspector verified that this circular is not applicable to Indian Point 3.
(Closed) 81-CI-03 Inoperable Seismic Monitoring Instrumentation - Pro-cedure 3PT-R37 Seismic Instrumentation has been revised to preclude the possibility of removal of all seismic instrumentation at.the same time.
7.
Followup on IE Bulletins i The inspector reviewed the following IE Bulletins.
In addition to his comments, he ascertained that: ' The written response was within the time period stated in the' - Bulletin.
The written response included the infomation required to be - reported.
! The written response includes adequate corrective action commitments - based on the infomation presented in the Bulletin and licensee's response.
The licensee's management forwarded copies of the written response
- to the appropriate onsite management representatives.
The information discussed in the licensee's written response was - accurate.
The corrective action taken by the licensee was as described in the - written response.
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(Closed) 77-BU-04 Calculation error affecting design perfomance of a system for controlling pH of the containment sump water following a LOCA.
The inspector reviewed caluclations perfomed by the licensee demonstrating that under LOCA conditions the sump pH would be within the recomended pH range of 8.5 to 10.0.
(Closed) 79-BU-05 and 05A Nuclear Incident at TMI. This bulletin was re-viewe. in Inspection Report 79-14 and later closed in Inspection Report 80-05.
(Closed) 79-BU-06 Review of Operational Errors and System Misalignments identified during TMI Incident. This bulletin was reviewed in Inspection Report 79-14 and later closed in Inspection Report 80-05.
(Closed) 79-BU-14 Seismic Analysis for As-Built Safety Related Piping Systems.
This bulletin was reviewed in Inspection Report 79-23 and later closed in Inspection Report 80-08.
8.
Licensee Event Reports (LER's) A.
In Office Review of Licensee Event Reports The inspector reviewed LER's submitted to the NRC:RI office to verify that details of the event were clearly reported, including the accuracy of the. description of cause and adequacy of correc-tive action.. The inspector detemined whether further infoma-tion was required from the licensee, whether generic implications were involved, and whether the event warranted onsite followup.
The following LER's were reviewed: Report Number Subject 82-001/01T-0 Primary to Secondary Leak in #33 Steam Generator 82-002/01T-0 Oval Shaped Hole in the Girth Weld of
- 32 Steam Generator l
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Onsite Licensee Event Followup
The LER's listed below were reviewed to verify that the reporting re-quirements of Technical Specifications and Station Administrative Procedures had been met, that appropriate corrective action had been taken, that the event was reviewed by the PORC (Plant Operating Review Committee), and that continued operation of the facility was in con-famance with the Technical Specification limits.
1) 82-001/01T-0 The unit has been shut down for a refueling outage.
Eddy current analysis is currently being performed. The licensee will require approval by the NRC in order to start up. See section 9 for more details.
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2) 82-002/01T-0 The licensee is currently conducting a program of ultrasonic and x-ray testing of the girth welds in #32 steam generator.
See section 10 for more details.
9.
Steam Generator #33 Tube Leak A.
Event: On March 24, 1982 a+ 9:50 p.m., the steam generator blowdown monitor alanned. Licensee evaluation identified an approximate 1.8 gpm primary to secondary leak in #33 steam generator. A routine shut-down was commenced and all control rods were in at 2:25 a.m., March 25,1982. The licensee declared an unusual event at 11:58 p.m.
March 24, 1982, because of a minor release to the atmosphere via the air ejector vent.
The duration of the release was 128 minutes and totaled 0.41 curies (noble gases) which is.21% of Technical Speci-fication allowable limits. The unit was subsequently cooled down, and the steam generator was entered to identify the leaking tube.
B.
Inspections by the Licensee to Date: . As of April 15, 1982, the leak has been identified in the cold leg, Row 19, Column 47, approximately 10" above the tube sheet.
Eddy current testing (ECT) was the method of identifying the height of the leak. ECT, to date, on #33 steam generator has the following results: Cold Leg 3054 tubes evaluated.
460 tubes 2 40% degraded but l less than 65% degraded.
256 tubes 2.65% degraded.
Hot Leg 569 tubes evaluated.
tubes ?_40% degraded but less than 65% degraded.
tubes 2_65% degrade. .
C.
Three types of steam generators inspections are required of the licensee as described below: Types of Inspection Requirements 1) Technical Specification Perfonned in the hot leg - Around the tube bend to the top Inservice Inspection Each - Refueling Outage.
of the support in the cold leg.
- Number of tubes to be inspected = 3xN% (where N=# of steam generators) 3x(4)% = 12% or 400 tubes.
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- 31 steam generator for this inspec-tion period.
Status: Not yet completed.
Perfomed in the hot leg (800 tubes).
2) Licensee Amendment #31 - All four steam generators.
Requires Inspection for - Gauging (denting) To the 6th support plate.
- - Results must be presented to the NRC for approval prior to startup.
Status: Completed in #33 steam generator. Two tubes have been - identified which failed to pass the 610 probe.
3) Licensee Amendment #41 - 100% of the cold leg to the 2nd Requires a Cold Leg support plate.
All steam generators.
Inspection - Results must be presented to the - NRC for approval prior to startup.
Status: #33 Steam Generator, See section 98.
- 32 Steam Generator: 1193 tubes evaluated.
101 tubes 2 40% degraded but less than 65% degraded.
51 tubes 2 65% degraded.
The inspector is being apprised, on a daily basis, as to the status of the inspection program.
No violations were identified.
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Steam Generator Closure Seam Indications and Program On March 27, 1982, a through wall leak was found,'during cold shutdown, in the #6 weld seam of the transition to shell in steam generator #32.
Nor destructive examination has been perfomed to establish the nature and significance of this defect.
Facts and Status of Evaluation 1) Through hole description: The exit point dimension is approximately 1/S" wide x 5/8" long, located at the top side of the 32-6 weld seam.
The defect is open through the vessel wall, as per Radiographic Testing (RT) and Ultrasonic Testing (UT).
2) UT of the weld seam #32-6, identified numerous UT indications. The majority of these indications are parallel to the weld seam, apparently located in the weld metal, or close to the weld metal. Some even appear to be below the weld in the transition shell assembly. Spot radio-graphy, using a 65 curie iridium source at'15" SFD, of the areas to the left and right of the through hole, definitely corrbborated the UT indications.
3) UT along seam #6 of #33 steam generator (33-6) for a dis:ance of 15" identified 9 indications similar to the longitudinal indications found in seam 32-6. The #6 seam of steam generators #31, 32, 33 and 34 were shop welded closure joints made by Outside Diameter (00) submerged arc, followed by Inside Diameter (ID) backgouging and manual stick electrode welding. These four seams have similar weld-ing fabrication histories. The licensee intends to UT inspect each seam, to detennine the extent of any additional indications.
4) The inspector observed UT inspection in progress on seam #32-6.
5) To date, a majority of the UT indications appear to be within the ID.
(25% of the material volume) During the exit meeting, the following factors were discussed: 1) The usefulness of a 3600 full circumference colbalt RT shot being performed on seam #32-6 as a basis for evaluation of the UT indi-cations, and also for comparison to the original as-fabricated radiographs, which were made in a similar manne. ....
2) To conduct a hardness test, traverses across the plate heataffected zone (HAZ) and weld metal, of the #6 weld seams.
3) To perform chemistry analysis of base plate and ID-0D of weld metal for seam #32-6.
4) The need for review of the Westinghouse data package, containing history of seam #6 for each steam generator.
5) UT procedure - The use of shear angles other than 45. The licensee is continuing comprehensive testing to determine the cause, character and scope of indications in the steam generator.
No violations were identified.
11.
Exit Interview At periodic intervals, during the course of the inspection, meetings were held with senior facility management to discuss the inspection scope and findings.
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