IR 05000353/1989012
| ML20246Q282 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/22/1989 |
| From: | Blumberg N, Marilyn Evans NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20246Q280 | List: |
| References | |
| 50-353-89-12, NUDOCS 8903290007 | |
| Download: ML20246Q282 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-353/89-12 Docket No.
50-353 License No. CPPR-107 Licensee:
Philadelphia Electric Company 2301 Market Street l
Philadelphia, PA 19101
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' Facility Name:
Limerick Generating Station, Unit 2 Inspection At:
Limerick, Pennsylvania Inspection Conducted:
February 24 - March 3, 1989 gga, //u 3 /ule 'l-
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Inspectors:
Michele G. Evaps, Reactor En f(fer, DRS date
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Approved by:
Norman J. Blumberg, Chief, OKerations date Section, Operations Branch, DRS Inspection Summary:
Inspection on February 24 - March 3, 1989 (Report No.
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50-353/89-12)
Areas Inspected: Routine, unannounced inspection of the overall power
.j ascension program including licensee action on previous inspection findings,
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procedure reviews, QA/QC interfaces and tours of the facility.
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Results:
Licensee preparations for the initial startup of the facility, including procedure issuance and training of startup test engineers, were reviewed and found to be progressing adequately.
In addition, 33 test-procedures were reviewed and determined to be acceptable.
The licensee's=
actions regarding previous inspection findings related to the initial startup.
program were found to be adequate and timely. No violations were identified.
Note: For acronyms not defined in this report, refer to NUREG-0544,.
" Handbook fo Acronyms and Initialisms."
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DETAILS'
1.0 Persons Contacted Philadelphia Electric Company
- D. DiPaolo, Superintendent, Unit 2 Quality Assurance E. Gibson, Superintendent,-Quality Support Section T.uGrim, Quality Support Engineer
- G. Kelly, Quality Assurance Engineer
- G. Lauderback, Supervisor, Unit 2 Startup Quality Control
- G. Tepper, Electrical Construction Engineer
- W. Ullrich, Manager, Unit 2 Startup General Electric
- A. Jenkins, Startup Test Program Supervisor NRC Personnel R. Fuhrmeister, Resident Inspector
- R. Gramm, Senior Resident Inspector
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The inspector also contacted other members of the licensee's Operations, Technical, Test and QA staffs.
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2.0 Licensee Action On Previous Inspection Findings l
(0 pen) Unresolved Item (50-353/89-09-01): Licensee to revise Startup Test Procedure STP-4.1, In Sequence Critical, to include limits on control rod withdrawal during initial criticality.
The inspector reviewed STP-4.1, Revision 1-B (Sub-PORC approved on March 1, 1989) and noted that the procedure had been revised to include calculation of the predicted critical position and reactivity anomaly limits prior to control rod withdrawal.
In addition, a note was added to
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the procedure, placing limits on control rod withdrawal if it appears that
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criticality may occur outside of the reactivity anomaly limits. The
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inspector found the changes to STP-4.1 to be acceptable.
However, this item will remain open pending final review of STP-4.1 by the Plant
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Ope'ations Review Committee (PORC).
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l (0 pen) Unresolved Item (50-353/89-09-02): Licensee to revise STP-70.0, Reactor' Water Cleanup System, and review the overall Startup Test Program
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to ensure that all testing has proper administrative controls.
The inspector reviewed STP-70.0, Revision 1-B (Sub-PORC approved on l
March 1, 1989) and verified that the procedure had been revised to include the applicable portions of preoperational test 2P-61.1.
In addition, the inspectc r verified through discussions with licensee
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representative that the overall Startup Tert Program had been reviewed to ensure that all testing done to meet requirements of Chapter 14 of the
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FSAR, has the same administrative controls as STPs.
Based upon the licensee review, no other STPs were found to need revision, and the licensee's actions to correct the deficiency were acceptab'le.
I However, this item will remain open pending final review of STP-70.0 by I
the PORC.
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3.0 Power Ascension Test Program (PATP)
3.1 Overall Power Ascension Test Program The inspector held discussions with the Startup Test Program Supervisor to determile the current status of the 158 Startup Test Procedures (STPs) needed to implement the PATP. At the conclusion i
of the inspection, 128 STPs had been presented to the NRC for review.
89 of the 128 STPs had received formal station approvals while the remaining 39 STPs had received all approvals with the exception of the plant manager.
The licensee's current schedule includes issuance of the remaining 30 STPs and final appreval of the 39 STPs which are scheduled to be presented to the NRC by early April 1989.
The inspector also discussed with the Startup Test Program Supervisor the status of licensee plans for training of startup test engineers prior to fuel load. The licensee's current plans include training on
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administrative procedures beginning in the middle of March and
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simulator training beginning in the middle of April 1989.
No unacceptable conditions were identified.
The inspector found the status of licensee procedures and plans for training of test engineers to be acceptable based upon a target fuel load date of June 1, 1989.
3.2 Power Ascension Test Procedure Review l
Procedure Review Scope l
The licensee's PATP test procedures of Attachment A were reviewed i
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 During review of STP-32.0, " Essential HVAC System Operation and Containment Hot Penetration Temperature Verification - Main Body",
the inspector questioned a licensee representative regarding the completeness of the references listed in the STP.
The inspector was e
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unable to find the various temperatures used as acceptance criteria in the STP in the references cited. The representative acknowledged the inspector's concern and stated that Revision 1 to STP-32.0 is currently being written in which the correct references are cited.
In addition, the inspector questioned the origin of a level two
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acceptance criteria for reactor pressure vessel skirt surrounding air temperature being maintained above a minimum of 70 F.
The licensee representative stated that the requirement was contained in GE Memo GE-0M-151, A. L. Jenkins to J. W. Spencer, dated November 30, 1984.
Upon review of this memo, the inspector noted that the air temperature of 70 F was only acceptable with an air velocity no greater than 6 ft/sec. However,' air. velocity is not measured in
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STP-32.0. Upon questioning the licensee representative, the
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inspector determined that the air velocity is measured in an air
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balance procedure during preoperational testing.
In addition, the representative stated that preliminary calculations made at the site, show that the air velocity will be greater than 6ft/sec. Therefore, GE site representatives have requested additional analysis from GE San Jose regarding the acceptability of the predicted values.
The inspector will continue to review this issue, following completion of the additional analysis by GE San Jose.
During review of STP-31.1, Loss of Turbine Generator and Offsite l
Power, the inspector specifically reviewed the procedure and Betchel i
Drawing No. 8031-E-1, Single Line Diagram, Station, to determine if
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precautions were being taken to' minimize the impact on Unit 1
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operations during conduct of this test.
The inspector verified that I
the initial plant electrical alignment was being changed from the normal plant alignment in order to minimize the impact on Unit 1.
In addition, special line-ups will be performed for the Service Water I
system and Fuel Pool Cooling and Cleanup System.
The inspector was I
satisfied that appropriate precautions will be taken to minimize the impact of the Unit 2 Loss of Turbine Generator and Offsite Power Test on Unit 1 operations.
During inspection 50-353/89-03, the inspector noted discrepancies in STP's 6.0, 6.1 and 10.0 which required changes to the GE Test Specification to correct the items.
During this inspection, the inspector reviewed Field Deviation Disposition Request (FDDR)
HH2-4448, Revision 3, dated February 18, 1989, and verified that appropriate changes were made to the GE Test Specification.
Conclusions The procedures reviewed were found to satisfy the attributes identified in Inspection Report 50-353/89-03 and to adequately meet i
the requirements and guidelines of the references.
No violations were identified.
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4.0 QA/QC Interfaces with the PATP I
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l The inspector held discu:sions with a. licensee representative regaiding-
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the Quality Support Group's review of the.STPs listed in Attachment A.
The inspector reviewed the licensee. representative's comment sheets'for those STPs, and discussed several of the comments with the representative.
i The comments appeared to indicate adequate QA review of STPs. No unacceptable conditions were identified.
5.0 Plant Tours The inspector made several tours of. vario'us areas-of the. facility including the reactor and turbine' enclosures, the control room'and'the remote shutdown panels to observe work in progress, housekeeping, cleanliness controls and status.of preoperational and construction y
activities. No unacceptable conditions were identified.
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6.0 Exit Interview
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At the conclusion of-the.' inspection on March 3, 1989 an exit meeting was held with licensee personnel (identified in Section 1.0) to di'scuss the inspection scope, findings and observations as detailed in this report.
At no time during this inspection were written inspection fincings 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 notucontain information subject to 10 CFR 2.790 restrictions.
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Attachment A
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Power Ascension Test Procedures Reviewed Startup Test Procedure (STP) - 1.0, Chemical and Radiochemical-Main Body,.
Revision 0, February 17, 1989 STP-1.1, Prefuel Load Data, Revision 0, February 17, 1989.
STP-1.2, Chemistry Data, Revision 0, February 17, 1989.
STP-1.3, Gaseous Effluent Sampling and Analysis, Revision 0, February 17, 1989.
STP-1.4, Reactor Water No Cleanup Test, Revision 0, February 17, 1989
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STP-1.6, Sample Station Operability, Revision 0,- February 17, 1989 STP-14.0, RCIC System - Main Body, Revision 0, February 17, 1989
STP-14.1, RCIC Functional Demonstration CST to CST at 150 PSIG, Revision 0, February 17, 1989 STP-14.2, Functional Demonstration and Controller Optimization at Rated Pressure CST to CST, Revision 0, February 17, 1989 STP-14.3, Stability Check CST to CST at 150 PSIG, Revision 0, February 17, 1989 STP 14.4, Controller Optimization During RPV Injection at Rated Pressure, Revision 0, February 17, 1989
I STP-14.5, Stability Check CST to RPV at 150 PSIG, Revision 0, February 17, 1989 l
STP-14.6, RCIC Cold Quickstart at Rated Pressure - CST to RPV, Revision 0, February 17, 1980
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i STP-14.7, RCIC Surveillance Tests CST to CST, Revision 0, February 17,-1989'
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STP-14.8, RCIC Endurance Run, Revision 0, February 17, 1989 I
STP-14.9, Loss of AC Power, Revision 0, February 17, 1989 i
STP-20.0, Steam Production - Main Body, Revision 0, February 22, 1989
.j STP-20.1, Two Hour Demonstration, Revision 0, February 22, 1989
STP-20.2, 100 Hour Demonstration, Revision 0, February 22, 1989
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STP-28.0, Shutdown from Outside Control Room - Main Body, Revision 0, February 17, 1989
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STP-28.1, Reactor Shutdown to Hot Standby Demonstration, Revision 0, February 21, 1989
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STP-28.2, Reactor Cooldown Demonstration, Revision 0, February 21, 1989
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STP-29.0, Recirculation Flow Control System - Main Body, Revision 0, February 22, 1989 STP-29.1, Local Manual Recirc Flow Control, Revision 0, February 22, 1989 STP-29.2, Master Manual Recirc Flow Control, Revision 0, February 22, 1989 STP-31.0, Loss of Turbine Generator and Offsite Power - Main Body, Revision 0, January 11, 1989 STP-31.1, Loss of Turbine Generator and Offsite Power, Revision 0, January 11, 1989 STP-32.0, Essential HVAC System Operation and Containment Hot Penetration Temperature Verification - Main Body, Revision 0, January 19, 1989 STP-32.1, Primary Containment Temperatures, Revision 0, January 19, 1989 STP-32.2, Hot Penetration Concrete Temperature, Revision 0, January 11, 1989 i
STP-32.3, Control Enclosure Temperature and Relative Humidity, Revision 0,
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January 11, 1989 STP-32.4, Control Room Temperature and Relative Humidity, Revision 0, January 11, 1989 STP-32.5, Reactor Enclosure and Main Steam Tunnel Temperature, Revision 0, January 11, 1989 l
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Attachment B
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-l References Regulatory Guide 1.68, Revision 2, August 1978, " Initial Test Program for
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Water Cooled Nuclear Power Plant"
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Regulatory Guide 1.68.2, Revision 1, < July 1978, " Initial Startup Test-
- Program to Demonstrate Remote Shutdown Capability for Water Cooled'
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Nuclear Power Plants" l
ANSI N18.7-1976, " Administrative Controls and Quality Assurance for
Operations Phase of Nuclear Power Plants."
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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 ~ Ur.its 1 and 2."
Limerick Generating Station A-200, Startup Test Procedure. Format and
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Content, Revision 2.
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Limerick Generating Station A-201, Startup Test Procedure Control,
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Limerick Generating Station A-202, Startup Test Implementation,
Revision 6.
Limerick Generating. Station A-203, Startup Test Program Personnel
Training and Qualification, Revision 1.
Betchel Drawing No. 8031-E-1, Revision 13, LGS Units 1 and 2, Single Line-
Diagram, Station.
J GE Memo, GE-0M-151, A. L. Jenkins to J. W. Spencer, dated November 30,
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1984.
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