IR 05000353/1989009
| ML20235Y868 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/01/1989 |
| From: | Blumberg N, Marilyn Evans NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20235Y848 | List: |
| References | |
| 50-353-89-09, 50-353-89-9, NUDOCS 8903140655 | |
| Download: ML20235Y868 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-353/89-09 Docket No.
50-353 License No,'
CPPR-107 Licensee: Philadelphia Electric Company 2301 Market Street
' Philadelphia, Pennsylvania 19101
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Facility Name:. Limerick Generating Station, Unit 2 Inspection At:
Limerick, Pennsylvania Inspection Conducted: January 31 - February 7, 1989 Inspectors:
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Michele G. F(vans, Reactor /gineer, DRS date Approved by:
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Norman J.-Blumberg, Chief Operations date Section, Operations Branch, DRS Inspection Summary:
Inspection on January 31 - February 7,1989 (Report
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No. 50-353/89-09)
Areas Inspected: -Routine, unannounced inspection of the overall power ascension program including training for test engineers, procedure reviews,
.QA/QC interfaces and tours of the-facility.
Results: Two unresolved items were identified.
First, STP 4.1, in sequence critical, was found to lack appropriate steps limiting control rod withdrawal during initial criticality. The second unresolved item involved the need to revise-STP 70.0 and review the Startup Test Program to ensure that all testing done to meet the requirements of FSAR Chapter 14, has the same administrative controls as STPs.
No' violations were identified.
NOTE: For acronyms not defined in this report, refer to NUREG-0544, " Handbook of Acronyms and Initialisms".
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DETAILS 1.0 Persons Contacted Philadelphia Electric Company
- J. Corcoran, Superintendent, Unit 2 Start-Up Support
- K Folta, Superintendent,- Quality Assurance Section
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E. Gibson, Superintendent, Quality Support Section
- G. Lauderback, Supervisor, Unit 2 Start-Up Quality Control
- A. S. MacAinsh, Manager, Limerick Quality
- J. McElwain, Superintended.t, Technical Monitoring
- W. Ullrich, Manager, Unit 2 Start-Up
- H. Wiegle, Superintendent, Unit 2 Start-Up Operations General Electric D. Atkinson, Startup NSSS Test Supervisor
- A..Jenkins, Startup Test Program Supervisor K. Picard, Startup Test Engineer NRC Personnel
- R. Fuhrmeister, Resident Inspector
.R. Gramm, Senior Resident Inspector
- Denotes those present at the exit meeting on February 7,1989.
The inspector also contacted other members of the licensee's Operations,
. Technical, Test and QA staffs.
. 2.0 Power Ascension Test Program (PATP)
2.1 Overall Power Ascension Test Program The inspector held discussions with the Startup Test Program Super-visor and the Startup NSSS Test Supervisor to review licensee plans for training of startup test engineers prior to fuel load. General training on the administrative procedures and the startup test procedures (STPs) will be conducted for all test engineers.
In addition, simulator training on specific STPs is being planned.
The simulator training will be conducted specifically for the test engineers alone and also for the test engineers with a crew of licensed operators.
No unacceptable conditions were identified. The inspector will further review startup training by attending both simulator and classroom sessions during a future inspection.
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3-2.2 Power Ascension Test Procedure-Review-Procedure Review Scope The licensee's PATP test' procedures of Attachment'A were reviewed-for-their-conformance to the requirements and guidelines of the references listed in Attachment B and for the applicable attributes listed in Inspection Report 50-353/89-03 Section 2.2.
Findings Initial Criticality / Full Core Shutdown Margin Demonstration The inspector reviewed the approved startup test procedure, STP-4.1, In Sequence Critical, in detail. This procedure encompasses initial
. criticality and demonstrates conformance to the technical specifica-tion limits for shutdown margin and reactivity anomalies.
During-this review the inspector noted that the procedure did include the performance of a predicted critical calculation prior to withdrawing control rods. However, a calculation of the reactivity anomaly band in terms of control rod notches withdrawn is not performed. prior to withdrawing control rods.
Instead, the procedure includes perfor-mance of this calculation as part of the analysis after initial criticality is achieved.
In addition, the inspector noted that the procedure did not-place limits on control rod withdrawal if'critica-lity is.not achieved within the predetermined limits. The inspector
. discussed these findings with the Startup Test Program Supervisor and a Startup Test Engineer, who agreed to revise STP 4.1 to insure that the above deficiencies are corrected.
This item is considered unresolved (353/89-09-01) pending revision of STP 4.1 and further review by the inspector.
Riactor Water Cleanup System
~~ TSinspectorreviewedtheapprovedstartuptestprocedureSTP-70.0, Reactor Water Cleanup System - Main Body. This test demonstrates specific aspects of the mechanical operability of the Reactor Water Cleanup (RWCU) System. During this review, the inspector noted that the hot shutdown mode of RWCU was not tested in STP-70.0, however, FSAR Table 14.2-3 still discussed demonstration of hot shutdown mode operation.
Instead, STP-70.0 states that adequate net positive suction head (NPSH) for the RWCU recirculation pumps, which is the primary purpose of the hot shutdown mode testing, is conducted in 2P-61.1', RWCU System preoperational test. The inspector reviewed 2P-61.1 and concurred with the licensees determination that the calculations for NPSH were acceptable and more conservative than doing NPSH per ST P-70.0.
The inspector discussed the issue of transferring the NPSH test from STP 70.0 to 2P-61.1 with the Startup Test Program Supervisor and the Unit
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2 Startup Manager who stated that PEco licensing had made a decision.
not to delete the shutdown mode testing discussions from FSAR Table 14.2-3, but instead to provide a " paper trail" using the STP to
indicate that the NPSH determination is done in 2P-61.1. Therefore,
-l the.. licensee was using a preoperational test procedure to meet the-
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requirements of the Startup Test Program described in the FSAR.
The inspector questioned the licensee representatives regarding the administrative controls governing preoperational test procedures.
The licensee representatives stated that preoperational test procedures and results were not reviewed and approved by the Plant Operations Review Committee (PORC), which is the case for all STPs.
Therefore, the licensee representatives agreed that STP-70.0 would need to be revised to include applicable portions of 2P-61.1 to ensure PORC review and approval.
In addition, the licensee representatives agreed to review their-Startup Test Program, to ensure that all testing done to meet requirements of Chapter 14 of-the FSAR, has the same administrative controls as STPs. This item is considered unresolved (353/89-09-02)'pending completion of licensee actions and further review by the-inspector.
Conclusions No violations were identified..The procedures reviewed were found-to satisfy the above attributes and to-adequately meet the require-ments and guidelines of the references with the exception of the two unresolved items noted above.
3.0 QA/QC Interfaces with the PATP The inspector held discussions with a licensee representative regarding the Quality Support Group's review of Startup Test Procedures (STPs).
The representative. stated that all STPs are reviewed to determine that all FSAR and GE Test Specification requirements are met..He stated that the review conducted was more of an administrative review than'a technical' review. The inspector discussed several specific STP's with the licensee representative and reviewed his comment sheets for those STPs. No unacceptable conditions were identified.
4.0 Plant Tours The inspector made several tours of various areas of the facility to observe work in progress, housekeeping, cleanliness controls and status of preoperational and construction activities, No unacceptable conditions were identified.
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I 5'0' Unresolved Items
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Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, items of noncompliance or deviations. Unresolved items disclosed during this inspection are
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discussed in Section 2.2.
6.0 Exit Interview At the conclusion of the inspection on February 7,1989 an axit 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.
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Attachment A-
' Power Ascension Test Procedures Reviewed f
Startup Test Procedure (STP)-4.0, Shutdown Margin Demonstration - Main Body, i
Revision 0, January 17, 1989
..STP-4.1, IN Sequence Critical, Revision 0, January 17, 1989.
STP-9.0, Water Level Reference LEG Temperature - Main Body,. Revision 0, January 17, 1989.
STP-9.1,. Reference Leg Temperature Comparison, Revision 0, January 17, 1989 STP-22.0, Pressure Regulator - Main Body, Revision 0,. January 17, 1989.
STP-22.1, Pressure Regulator Response'- Control Valve Operation, Revision 0, January 17, 1989.
-STP-22.2, Pressure Regulator Response - Control and Bypass Valve Operation,
' Revision 0,- January' 17, 1989 STP-22.3, Pressure Regulator Response - Bypass Valve Operation, Revision 0, January 17, 1989 STP-27.0, Main Turbine Trip - Main Body, Revision 0, January 17, 1989 STP-27.1, Turbine Trip Within Bypass Va?ve Capacity,' Revision 0, January 17, 1989 STP-27.2, Bypass Valves Capacity Check, Revision 0, January 17, 1989
. t STP-27.4, Turbine Trip at'TC6, Revision 0, January 17, 1989 STP-30.0, Recirculation System - Main Body, Revision 0, January 17, 1989 STP-30.1, Recirculation System, One Pump Trip, Revision 0, January 17, 1989 STP-30.2, Recirculation Pump Trip (RPT) of Two Pumps, Revision 0, January 17, 1989 STP-30.3, Recirculation System' Performance, Revision 0, January 17, 1989 STP-34.0, Offgas Performance Verification - Main Body, Revision 0, November 25, 1988 STP-34.1, Offgas Performance Verification, Revision 0, November 25, 1988
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STP-35.0, Recirculation System Flow Calibration - Main Body, Revision 0,-
January 17, 1989 i
STP-35.1, Recirculation System Flow Calibration, Revision 0, January 17, 1989 STP-35.2, Recirculation System Flow Limiter Adjustment, Revision 0, January 17, 1989 STP-70.0, Reactor Water Cleanup System, - Main Body, Revision 0, September 2, 1988 STP-70.1, Blowdown Mode Performance Verification, Revision 0, September 2, 1988 STP-70.3, Normal Mode Performance Verification, Revision 0, September 2, 1988 STP-71.0, Residual Heat Removal System - Main Body, Revision 0, November 25, 1988 STP-71.1, Suppression Pool Cooling Mode, Revision 0, November 25, 1988 i
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Attachment B
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References'
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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 Ge$erating 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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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
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Limerick Generating Station A-203, Startup Test Program Personnel Training and Qualification, Revision 1.
Letter GE-SM-539, A.L. Jenkins. to W. T. Ullrich, dated April 6,1988, re:
Power Ascension Test Program Impact on FSAR.
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