IR 05000353/1989003
| ML20235F846 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/14/1989 |
| From: | Blumberg N, Marilyn Evans NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20235F840 | List: |
| References | |
| 50-353-89-03, 50-353-89-3, NUDOCS 8902230028 | |
| Download: ML20235F846 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-353/89-03
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Docket No.
50-353 License No.
CPPR-107 Licensee:. Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101
. Facility Name:
Limerick Generating Station, Unit 2 Inspection At:
Limerick, Pennsylvania
. Inspection Conducted: January 9-19, 1989 Inspectors: DM
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Michele G. Evans, Reactor Engineer date Division of. Reactor Safety-Approved by:
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Y Norman J. B16mberg, Chief J'
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Operations Section, Operations Granch, DRS Inspection Summary:
Inspection on January 9-19,* 1989 (Report No. 50-353/89-03)
Areas Inspected:
Routine, unannounced inspection of the overall power ascension program including procedure reviews, QA/QC interfaces and tours of the facility.
Results:
No violations were identified.
Licensee' preparations for the initial startup of the facility were reviewed and determined to be far advanced relative to a projected fuel load date of June 1,1989.
128 of 159 startup test procedures were provided to the inspector for review prior to the conclusion of the inspection.
Thirty test procedures were reviewed and determined to be adequate.
Preparations for startup including staffing of the startup organization and QA/QC plans for monitoring and reviewing test results-l were found to be progressing adequately.
j Note:
For acronyms not defined in report, refer to NUREG-0544, " Handbook of Acronyms and Initialisms."
gRo2230028 890214 o
ADOCK 05000353 PDC b
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L DETAILS 1.0 Persons Contacted Philadelphia Electric Company D. Di Paolo, Superintendent, Unit 2 Quality Assurance (QA).
G. Edwards, Operations Transition Manager J. Hutton, Start-Up Operatione Coordinator G. Lauderback, Supervisor, Unit 2 Start-Up Quality Control-A. S. MacAinsh, Manager, Limerick; Quality J. McElwain, Superintendent, Technical Monitoring
- J. Mehaffey, QA Engineer R. Stipcevich,. Project Engineer G. Tepper,. Electrical Construction Engineer
- W. Ullrich,: Manager, Unit.2 Start-Up
- H. Weigle,~ Superintendent, Unit 2 Start-Up Operations General Electric
- D. Atkinson, Start-Up NSSS Test. Supervisor J
- A. Jenkins, Start-Up Test Program Supervisor
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NRC! Personnel
- R. Fuhrmeister, Resident Inspector
- R. Gramm, Senior' Resident Inspector
- Denotes those present at the exit meeting on January 19, 1989.
The inspector also contacted other members of the licensee's Operations, Technical, Test and QA/QC staffs.
2.0 Power Ascension Test Program (PATP)
2.1 Overall Power Ascension Test Program Scope The documents used as references during this inspection are listed in Attachment A.
The inspector reviewed the administrative procedures listed in Attachment B.
The inspector also held discussions with the Startup Test Program Supervisor and the Startup NSSS Test Supervisor to review the approaches to be taken to assure adequate administration of the power ascension test program and to determine the current status of the power ascension test procedures necessary to implement the test program as defined in Chapter 14 of the FSAR.
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The inspector. verified that administrative measures have~been established to assure the following:
- Test procedures are current prior:to use.
- Test personnel are knowledgeable.
- Controls exist for' test procedure changes.
- Interruption in-tests ~are controlled.
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- Tests are properly coordinated.
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- Unusual events and test deficiencies are documented.
- Tests are scheduled.
- Test results are reviewed.
- Test acceptance criteria are defined.
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- Proper retest and review are accomplished following test deficiency.
. correction.
Findings The licensee's administration program was' determined to satisfy the above attributes. The licensce's administrative program' utilizes features from other recent startup programs and also utilizes normal station administrative controls were practicable.
Of the 159 Startup Test Procedures-(STPs) needed to implement the PATP, 128 STPs had been transmitted to'the Senior Resident Inspector for NRC review at'the conclusion of this inspection.
64 of the 128'STPs had received formal station approvals while the remaining 64 STPs had received
- all approvals with the exception of the plant manager.
. The licensee had not finalized its staffing plans for the startup test organization, and will not do so until a later date, which is closer to the estimated fuel load date.
Staffing will be further reviewed by the inspector during a subsequent inspection.
Conclusions No unacceptable conditions were identified.
The licensee's administrative controls, procedure status and staffing plans were found to be adequate.
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_4 2.2. Poy9r Ascension Test Procedure Review Prccedure Review Scope The licensee's PATP test procedures of Attachment C were reviewed for their conformance to the requirements and guidelines of the references
. listed in Attachment A and for the following attributes:
- Appropriate management review ar.d approval has been accomplished.
- Appropriate committee review has been accomplished.
- Procedure is in the proper format.
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- Test objectives are clearly stated and consistent with the FSAR.
- Appropriate references are listed.
- Appropriate prerequisites and precautions have been included.
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- Initial test conditions are specified.
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- Acceptance criteria are clearly stated.
- Provisions have been made to identify test equipment utilized.
- Provisions have been made to identify personnel performing the test.
- The procedure is technically adequate and workable.
- Temporary jumpers, installations and lifted leads are properly restored.
- Provisions have been made for recording, evaluating and approving test data.
- Provisions have been made to identify test deficiencies and exceptions and to document their resolutions.
Findings During review of STP's 6.0 and 6.1 the inspector noted a discrepancy between the STP acceptance criteria and the GE test specification regarding SRM count rate.
In addition, during review of STP 16.0, the inspector noted a discrepancy between the test conditions identified in the GE test specification compared to the actual test procedure.
The inspector discussed these discrepancies with the Startup NSSS Test Supervisor who acknowledged the inspector's concerns.
Changes to the GE test specification will be prepared to correct these items.
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.j Conclusions No unacceptable conditions were identified.
T.he procedures reviewed were found to satisfy the above attributes and to adequately meet the requirements and guidelines of-the references.
3.0 QA/QC Interfaces with the PATP The inspector held discussions with licensee representatives to determine the current involvement of QA/QC in the Power Ascension Test Program.
Review of.Startup Test Procedures (STPs) is being conducted by the licensee's Quality Support Group. Monitoring of power ascension testing uc will be performed by the licensee's Technical-Monitoring Group. The Guidelines for test monitoring are currently being developed. At the time of this inspection, the licensee had not determined which QA/QC-group would be responsible for STP results review.
The inspector will-further review QA/QC' involvement in power ascension test monitoring and STP results review in a future inspection following licensee formalization of their plans.
4.0 Plant Tours The inspector made several tours of various areas of the facility'to
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observe work in progress, housekeeping, cleanliness controls and status of construction activities.
No unacceptable conditions were identified.
- 5.0 Exit Interview At the conclusion of the inspection on January 19, 1989 an exit meeting was' held with-licensee personnel (identified in Section 1.0) to discuss the inspection scope, findings and observations as detailed in this report. At no time during this inspection were written inspection findings provided to the licensee by the inspector.
Based on NRC Region I review of this report and discussions held with licensee representatives during the inspection, it was determined that this report does not contain information subject to'10 CFR 2.790 restrictions, i
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. Attachment A References
- Regulatory Guide 1.68, Revision 2, August 1978, " Initial Test Program for Water Cooled Nuclear Power Plant."
ANSI N18.7-1976, " Administrative Controls and Quality Assurance for Operations Phase of Nuclear Power Plants."
- Limerick Generating Station Unit 2, Technical Specifications, DRAFT
- Limerick Generating Station Unit 2, Final Safety Analysis Report (FSAR), Chapter 14, " Initial Test Program."
= GE Specification, NEB 0 23A1918, Revision 2, "Startup Test Specification, Limerick Units 1 and 2."
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Attachment B Administrative Procedures Reviewed
- Limerick Generating Station A-200, Startup Test Procedure Format and Content, Revision 2.
- Limerick Generating Station A-201, Startup Test Procedure Control, Revision 2.
- Limerick Generating Station A-202, Startup Test Implementation, Revision 6.
- Limerick Generating Station A-203, Startup Test Program Personnel Training and Qualification, Revision 1.
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l Attachment C Power Ascension Test Procedures' Reviewed Startup Test-Procedure (STP) - 2.0, Radiation Measurements'- Main Body, Revision 0, November 25, 1988.
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STP-2.1, Radiation Surveys, Revision 0, November.25; 1988.
'STP-6.0,. SRM Signal to Noise Ratio and Minimum Count' Rata Determination, Revision 0, September. 22, 1988.
STP-6.1, SRM Signal to Noise Ratio and Minimum Count Rate Determination, Revision 0, September 22, 1988.
STP-6.2, Approach to Criticality - SRM Response to Control Rod Withdrawal, Revision 0, September 22, 1988.
STP-6.3, SRM Non-Saturation Demonstration, Revision 1, September 22, 1988.
STP-10.0, IRM Performance - Main Body, Revision 1, December 16, 1988.
STP-10.1, SRM/IRM overlap, Revision 1, December'16, 1988.
STP-10.2, IRM Range 6-7 Continuity, Revision 1, December 16, 1988.
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STP-10.3, IRM/APRM overlap, Revision 1, December 16, 1988 STP-11.0, LPRM Calibration - Main Body, Revision 0, January 11, 1989.
STP-11.1, Verification of Proper Connection of LPRM Detectors. and Readout Equipment, Revision 0, January 11, 1989.
STP-11.3, LPRM Calibration with Process Computer, Revision 0, January 11, 1989.
STP-11.4, LPRM Operational Verification During Rod Withdrawal, Revision 0.
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STP-12.0, APRM Calibration-Main Body, Revision 0, September 22, 1988.
STP-12.1, Constant Heatup Rate APRM Calibration, Revision 0, September 22, 1986.
STP-12.2, Low Power APRM Calibration, hevision 0, September 22, 1988.
STP-12.3, High Power APRM Calibration, Revision 0, September 22, 1988.
STP-16.0, Selected Process Temperatures-Main Body, Revision 0, September 22, 1988.
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STP-16.2, Bottom Head Drain Temperature, Revision 0, September 22, 1988.
STP-16.3, Recirculation Pump Trip Recovery Data, Revision 0, September 22, 1988.
STP-18.0, Trip Uncertainty - Main Body, Revi.sion 0, September 2, 1988.
STP-18.1, Trip Uncertainty - Determination, Revision 0, September 2, 1988.
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STP-24.0, Turbine Valve Surveillance - Main Body, Revision 0, December 16, 1988.
STP-24.1, Stop Valve Testing, Revision 0, December 16, 1988.
STP-24.2, Control Valve Testing, Revision 0, December 16, 1988.
STP-24.3, Bypass Valve Testing, Revision 0, December 16, 1988.
STP-26.0, Relief Valves - Main Body, Revision 0, September 2, 1988.
STP-26.1, Relief Valve Low Pressure Test, Revision 0, September 2, 1988.
STP-26.2, Relief Valve Rated Pressure Test, Revision 0, September 2, 1988.
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