IR 05000322/1980016
| ML20002C597 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 11/19/1980 |
| From: | Higgins J, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20002C594 | List: |
| References | |
| 50-322-80-16, NUDOCS 8101100542 | |
| Download: ML20002C597 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-322/80-16 Docket No. 50-322 License No. CPPR-05 Priority Category B
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Licensee:
Long Island Lighting Comoany 175 East Old Country Road Hichsville, New York 11801
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Facility Name:
Shoreham Nuclear Power Station, Unit 1 Inspection at:
Shoreham, New York Inspection conducted: Septembei-15-October 22, 1980 Inspectors: h
//!/4!?O J/ C. %) Jins, Senior Resident Inspector date signed date signed date signed Approved by:
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. B. Kister,Minief, Reactor Projects Section
/date/ signed No. 4, RO&NS Branch
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Inspection Summary:
l Inspections on:
September 15-October 22, 1980 (Inspection Report no. 50-322/80-16)
Areas Insoected: Routine onsite regular and backshift inspections by the resident inspector (79 inspection hours) of work activities, preoperational testing, and plant staff activities including:
tours of the facility; test witnessing; review of test procedures; review of IE Bulletins; review of Quality Assurance practices; review of personnel training; review of instrument calibration; and, followup on previous I
inspection findings.
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Resul ts :
No items of noncompliance were identified.
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l Region I Form 12 gev. April 77)
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DETAILS 1.
Persons Contacted J. Carney, Site Engineering Representative (S&W)
T. Czapleski, Training Coordinator (NES)
D. Durand, 0QA Engineer (L)
W. Gunther, I&C Engineer (L)
R. Gutmann, Maintenance Engineer (L)
J. Kelly, Field QA Manager (L)
W. Klein, Lead Startup Engineer (L)
L. Lewin, Assistant Startup Manager (L)
J. Forin, Senior Licensing Engineer (L)
J. Novarro, Project Manager (L)
J. Riley, Lead Startup Engineer (GE)
J. Rivello, Plant Manager (L)
J. Taylor, Startup Manager (L)
D. Terry, Lead Startup Engineer (L)
NES - Nuclear Energy Services
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- Long Island Lighting Company S&W - Stone and Webster GE - General Electric The inspector also interviewed other licensee and contractor personnel during the course of the inspection including management, clerical, maintenance, operations, engineering, testing, quality assurance and construction personnel.
2.
Previous Inspection Item Uodate (closed) Inspector Follow Item (322/76-10-14): Certification of Liquid Radioactive Waste Tank Capacities:
This item was raised in paragraph 4.h of inspection report 322/76-10.
The licensee has established checks of usable Radwaste Tank capacities in the individual Radwaste System pre-operational tests. For example PT.711.001 checks the capacity of the High Conductivity Liquid Radwaste Tanks.
This item is closed.
(closed) Inspector Follow Item (322/76-10-16):
Effluent and Process Radiation Monitors: This item was raised in paragraph 4.j of inspection report 322/76-10.
Both of these types of monitors will be tested in the preoperational test for the D11 system, Pt.630.001, " Process Radiation Monitoring System". This item is closed.
(closed) Inspector Follow Item (322/76-10-19):
Radiation Instrument Tests: This item was raised in paragraph 4.k of inspection report 322/76-10.
The personnel radiation monitoring and survey instruments will be tested in preoperational test, PT.712.001. This item is closed.
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(closed)InspectorFollowItem(322/76-10-20)d:.mlab'oratoryEquipment Testing: This item was raised in paragraph 4 iof inspection report 322/76-10. The radiochemistry laboratory equipment will be tested in preoperational test, PT.714.001.
This item is closed.
(closed)UnresolvedItem(322/7h-05-05):
Response to 0QA Audit Findings:
The inspector reviewed all outstanding audit responses and selected closed audit findings. All open items had completion dates in the future specified. When an item passed its original due date, new dates were established.
The inspector also noted that the licensee has established a monthly surveillance of Audit Response Follow-up Actions to ensure that Audit Findings are being croperly addressed.
This item was also reviewed in insdection reports 79-16, 80-06 and 80-11 and is considered closed.
(closed) Unresolved Item (322/79-23-01): Update of Operational Quality Assurance (0QA) Procedures to agree with current practices: The inspector reviewed 00A Procedure OAI-15.1-01, Rev. 3 and noted that LILC0 Deficiency Report (LDR's),in accordance with current use, are reserved for significant deficiencies. The inspector also noted that 0QA Procedure 0AI-10.4-01, had been revised (Rev. 1) to specify that Repair / Rework Requests are initiated by the Startup Test Enginaer and reviewed by Station 00A.
Rev. 1 also removed the outdated form and references the Startup Manual for the correct form.
This item is closed.
(closed) Inspector Follow Item (322/80-09-04).
Training for Design Personnel in the Site Engineering Office (SEO): The licensee's representative approved SNPS Project Procedure No. 35, titled " Training on Project", which details the requirements for training of design personnel.
The inspector reviewed the procedure, the schedule of training to be conducted in accordance with the procedure, and records of training already completed.
The inspector also attended one training session.
This item is closed.
3.
Plant Tour The inspector conducted periodic tours of accessible areas in the plant during normal and backshift hours.
During these tours, the following specific items were evaluated:
-- Hot Work: Adequacy of fire prevention / protection measures used.
-- Fire Equipment: Operability and evidence of periodic inspection of fire suppression equipment.
-- Housekeeping: Minimal accumulations of debris and maintenance of required cleanness levels of systems under or following testing.
-- Equipment Preservation: Maintenance of special precautionary measures for installed equipment, as applicable.
-- Component Tagging:
Implementation and obsefvance of equipment tagging for safety, equipment protection, and jurisdiction.
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-- Instrumentation: Adequate protection for installed instrumentation.
-- Logs:
Completeness of logs maintained.
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-- Security: Adequate site constru: tion security.
-- Prohibited Items: Observations to determine no smoking in restricted areas and no alcoholic beverages on site.
-- Weld Rod Control: Observations to determine weld rod was being controlled in accordance with site procedures.
Minor problem areas were discussed with licensee representatives throughout the inspection.
No items of noncompliance were identified.
4.
Test Witnessing The inspector witnessed portions of CG.000.007, " Low Voltage Control" performed on the Remote Shutdown Panel (C61 System) and portions of CG.000.004, " Instrument and Control Component Checkout and Calibration" performed on instrumentation from the Control Rod Drive (C11) System.
During the tests, the inspector noted that:
-- the test procedures were properly approved;
-- test procedures were in use by personnel performing the test;
-- test equipment was calibrated;
-- test personnel were suitably qualified;
-- quality assurance participation was as required;
-- data was properly logged; and
-- test acceptance criteria were met for portions observed.
With the exception of items discussed elsewhere in this report, the inspector identified no discrepancies.
5.
Operational Ouality Assurance Audits The inspector reviewed the pertinent controlling procedures and standards and Audits completed by Operational Quality Assurance (0QA) from April, 1980 to the present.
Each audit package contained check lists describing the areas audited and the specific items reviewed. Also included were the Audit findings and corrective actions to address the findings as subnitted by the audited organization. The inspector also reviewed all open audit findings particularly with regard to promptness of followup action and action due dates. A sampling of closed audit findings was reviewed to determine that closure were proper.
No discrepancies were identified.
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6.
Training The inspector reviewed the following documents relating to the license's personnel training program at Shoreham:
-- ANSI N45.2.6-73, " Qualifications of Inspection, Examinations, and
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Testing Personnel for the Construction Phase of Nuclear Power Plants"
-- Regulatory Guide 1.58-73, " Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel".
-- Shoreham FSAR, Chapters 13 and 14.
-- Test Personnel Qualification File
-- Startup Manual
-- SP 12.014.01, Personnel Training Requirements.
-- SP 12.014.02, Training and Qualification Folders The inspector discussed the scope and content of the training programs for various categories of personnel onsite with the cognizant supervisors and training coordinators. The pre-licensing training program for reactor operators is now in a detailed system checkout phase. Additionally, six day simulator refresher courses are now being conducted for operators who have already been through the defined cold license program.
I&C Technician training is being conducted on a case basis as pertinent vendor courses are available. The permanent plant mechanics have just
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recently reported to the site and are beginning a 20 week training program.
The inspector reviewed training records for selected personnel to verify that education, training and experience was completed as required and was properly documented.
The inspector also attended selected training conducted onsite. With the exception of an apparent discrepancy in the period of test personnel certification, which was concurrently identified in an 0QA Audit, the inspector had no further questions at this time.
7.
Preoperational Program Imolementation a.
Repair / Rework Requests The inspector reviewed the requirements for Repair / Rework Requests in the Startup Manual and 0QA Procedures.
For the Remote Shutdown Panel (C61 System), the inspector reviewed all Repair / Rework Requests which had been issued.
Several had been satisfactorily completed while the rest remained outstanding. During tours of the plant the inspector questioned personnel working on equipment which had been turned over to the Startup Group.
In all cases identified, work was being done in accordance with approved procedures or a Repair / Rework Request.
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b.
LILC0 Deficiency Reports (LDR's)
The inspector reviewed the StartJp Manual and 0QA Procedures governing the generation of LDR's.
The LDR is a document used by the Startup Staff to report and document detected nonconformances and to obtain necessary corrective action.
The inspector also reviewed the various computer sorts available for LDR's, all 1980 closed LDR's, and all currently open LDR's.
The inspector noted that a significant number of LOR's existed for Metering and Test Equipment (M&TE) and discussed this area with responsible plant personnel.
Several steps have been and are still being taken to address this area.
Some of the LDR's were apparently written unnecessarily, and so procedures have been revised to change the methods of administratively handling M&TE.
Required tolerances and calibration intervals were re-evaluated and revised to improve M&TE performance. Additionally some steps were taken to better control handling and issuance of MATE.
The inspector had no further questions at this time.
8.
Inspection and Enforcement (IE) Bulletins a.
Bulletin 79-15 Bulletin 79-15, Deep Draft Pump Deficiencies, described internal deficiencies associated with deep draft pumps by various manufacturers used in safety related applications.
LILCO responded to this Bulletin in letters SNRC-428 and 436, and stated that the four service water pumps were the only such deep draft pumos onsite and that they would receive an all encompassing Startup Test Program. The inspector reviewed various correspondence and tests from Bingham-Willamette, the service water pump manufacturer; PT.122.001, " Service Water System Preoperational Test"; and, the preventive maintenance program for the service water pumps.
The inspector noted that the manufacturer performs a hydraulic test of the pump lasting a few hours, which demonstrates that the pump neets its design capacities. After this test, the pump is disassemaled and inspected.
The inspector also noted that no documented long-term pump runs were performed by the manufacturer either on prototype pumps or the Shoreham pumps; and that no long term pump runs followed by pump disassembly and inspection were scheduled by the licensee.
The licensee's representative stated that the Startup Program would run the pumps intermittently for about six months prior to performing the preoperational test.
Run time meters would be used to document pump accumulated running hours.
Vibration measurements would be made on the pumps to determine whether further actions such as pump disassembly and inspection were required. The first regularly scheduled overhaul, involving disassembly, will not occur for several years. The inspector stated that this Bulletin would remain open pending review of vibration data taken on the service water pumps during the Startup Program.
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Bulletin 79-18, Audibility Problems Encountered on Evacuation of Personnel from High-Noise Areas, describes problems that personnel had in hearing evacuation warnings while in high ambient noise areas
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of the plant. The inspector reviewed PT.319.001, " Plant Communications; SP.27.319.01, " Emergency Communications Check";the FSAR; and, System Descriptions. The licensee's procedures correctly check each loud speaker and alarm in the plant but not during tne condition of maximum anticipated noise as described in the Bulletin.
This Bulletin remains open.
9.
Instrument Calibration a.
General The inspector reveiwed the following documents and records associated with instrument calibration:
-- Startup Manual
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-- CG-000.004-4, Instrument or Control Component Checkout and Calibration. (CG-4)
-- CG-000.005-2, Loop Check. (CG-5)
-- CG-000.020-1 Electrical Switchboard Instruments (CG-20)
-- SP-41.002.01, Rev. 2, Process Instrument Record System.
-- Selected completed CG data sheets for Systems G-11, P-11, P-42, P-50, R-42, N-71 and P-21.
The records were reviewed to determine if instruments were being calibrated to the required accuracy using test equipment with traceable certification and in accordance with approved procedures.
With the exception of the below items, the inspector identified no discrepancies.
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Data Sheet Format The instrument calibration data sheets used for CG-4 and SP-41.002.01 do not have a specific provision for entering a desired output value, thus creating a potential for calibration errors when desired output
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values are different from input values. This could occur as a result l
l of different units, different spans or non-linear instrument response.
l This item is designated as inspector follow item no. (322/80-16-01).
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Instrument Tolerances Instruments supplied by other than General Electric have no calibration tolerances specified by the designer.
Discussions with cognizant personnel revealed that current responsibility for determining the required tolerances rests with the individual test engineers. The inspector noted that there is no well-defined method for establishing the required tolerances and that in some cases calibrations had been completed without establishing any tolerances.
The licensee's representative has temporarily established 2% of full scale as the tolerance when none can be determined by the test engineer.
This item is unresolved and is designated item no. (322/80-16-02).
d.
Test Results During the review of the completed test results' data packages from CG-4,5 and 20, the inspector noted several discrepancies, for example:
required accuracy not specified; method of calibration per step 7.3 of CG-4 not specified; desired output values not given; calibrations not done for increasing and decreasing values; instruction / vendor manual not specified per step 3.3 of CG-4; slightly out of specification value accepted with no explanation; values written over; data recorded in pe1cil; and, output units not specified.
Based on these findings, the Startup Manager issued a memorandum to all Lead Startup Engineers pointing out the problem areas and requirements.
This item is unresolved pending further review of
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past and future data packages and is designated as item no. (322/80-16-03).
10.
Unresolved Items Areas for which more information is required to determine acceptability are considered unresolved.
Unresolved items are contained in Paragraph 9 of this report.
11. Management Meetinas At periodic intervals during the course of this inspection, meetings were held with senior plant management to discuss the scope and findings of this inspection.
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