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| {{Adams | | {{Adams |
| | number = ML20215F225 | | | number = ML20236P171 |
| | issue date = 06/08/1987 | | | issue date = 08/05/1987 |
| | title = Insp Rept 50-353/87-06 on 870504-15.Deviations Noted: Licensee Has Not Provided Evidence to Demonstrate Completion of Design Changes Required or Physical Installations to Provide for Required Voltage Levels to Class 1E Components | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-353/87-06 |
| | author name = Anderson C, Woodard C | | | author name = Johnston W |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | addressee name = | | | addressee name = Kemper J |
| | addressee affiliation = | | | addressee affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| | docket = 05000353 | | | docket = 05000353 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-353-87-06, 50-353-87-6, IEIN-77-01, IEIN-77-1, IEIN-82-04, IEIN-82-4, NUDOCS 8706220285 | | | document report number = NUDOCS 8708120239 |
| | package number = ML20215F191 | | | title reference date = 07-14-1987 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 9 | | | page count = 2 |
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| U.S. NUCLEAR REGULATORY COMMISSION
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| Report No, 50-353/87-06 Docket N License No. CPPR-107 Priority - - Category B Licensee: Philadelphia Electric Company 2301 Market Street Philadelphia, PA 19101 Facility Name: Limerick Nuclear Generating Station, Unit 2 Inspection At: Limerick Generating Station Inspection Conducted: May 4-15, 1987 Inspectors: E [/#b Deg & /SB7 Carl H. Woodard',~ Reactor ' Engineer date
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| Approved by: C 37 C. JUAnderson, Chief Plant Systems date !
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| Section, DRS Inspection Summary: Inspection on May 4-15, 1987 (Inspection Report No. 50-353/87-06)
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| Areas Inspected: Routine, onsite, unannounced inspection by one region-based i inspector of activities pertaining to the safety-related electrical systems !
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| and component Results: One deviation and two unresolved items were identifie 'l 8706220265 870615 3 j PDR ADOCK 0500 G
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| | . I AUG 0 51987 i Docket N Philadelphia Electric Company ATTN: Mr. John S. Kemper Senior Vice President Engineering and Production 2301 Market Street Philadelphia, PA 19101 Gentlemen: |
| | Subject: Inspection No. 50-353/87-06 This refers to your letter dated July 14, 1987, in response to our letter dated June 15, 198 Thank you for informing us of the corrective and preventive actions cocumented in your letter. These actions will be examined during a future inspectio Your cooperation with us is appreciate |
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| DETAILS 1.0 Persons Contacted i l
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| 1.1 Philadelphia Electric l
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| * G. Lauderback, Quality Assurance Branch Head
| | Ori 8inal Signed B 3 j |
| * P. Naugle, Assistant Construction Superintendent | | William V. Johnston, Director l |
| * J. Harding, Lead Facility Engineer
| | , Division Reactor Safety cc w/ encl: |
| * T. Tucker, Quality Assurance Engineer
| | S. J. Kowalski, Vice President, Engineering and Research W. T. Ullrich, Superintendent, Limerick 2 Project j J. M. Corcoran, Quality Assurance Manager Troy B. Conner, Jr. , Esquire Eugene J. Bradley, Esquire, Assistant General Counsel Public Document Room (PDR) |
| * J. Corcoran, Manager, Quality Assurance
| | Local Public Document Room (LPDR) l Nuclear Safety Information Center (NSIC) . |
| * P. DiPaolo, Quality Assurance Branch Head G. Tepper, Electrical Engineer W. Shraff, Electrical Department Branch Head W. Coyle, Electrical Project Engineer C. Tuttle, Electrical Project Engineer R. Panunto, Electrical Facilities Engineer T. Dey, Quality Assurance Enginee .2 Bechtel
| | NRC Resident Inspector - |
| * W. Bradley, Quality Assurance Engineer
| | Commonwealth of Pennsylvania i |
| * S. Loofbourrow, Quality Assurance Engineer
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| * G. Kelly, Quality Assurance Engineer
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| * D. Harder, Qaulity Assurance Engineer
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| * B. Mukherjee, Project Engineer M. Drucker, Quality Assurance Engineer G. Bell, Quality Assurance Engineer G. Konecny, Quality Assurance Engineer K. Stout, Quality Assurance Engineer M. Dixon, Cable Yard Foreman M. Twardowski, Lead Long Term Maintenance Engineer R. Sewell, Electrical Engineer N. Roy, Electrical Engineer J. Schwamb, Lead Maintenance Quality Assurance Engineer 1.3 Nuclear Regulatory Commission
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| * R. Gramm, Senior Resident Inspector
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| * J. Kaucher, Resident Inspector
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| * Attendees at exit interview on May 14, 198 .0 Procedure Review A sample of the licensee's documents associated with the procurement, storage, installation and inspection of the class IE electric system components including wire and cable as listed in Attachment A were reviewed by the inspecto .
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| | B708120239 B70B05 PDR ADOCK 05000353 0 PDR OFFICIAL RECORD COPY RL LIM 2 87-06 - 0001. /05/87 i |
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| j This review was to ascertain whether the technical elements of the
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| licensee's safety analysis report (SAR) and NRC requirements had been adequately translated into applicable documents. Also, to determine if the construction specifications, drawings, work procedures and instructions were of sufficient detail and clarity to perform and control the work, No deficiencies were identifie .0 Record Review A sample of licensee records, associated with the class IE electric systems was reviewed by the inspector. These records are listed in Attachment This review was to ascertain the effectiveness of the licensee quality assurance program in the areas of procurement, storage, work activities and inspection of the class IE electric systems to assure that the systems and components perform their safety-related function No deficiencies were identifie .0 Electrical Components and Systems - Work Observation The inspector observed work in progress and completed work to determine whether activities related to safety-related electrical systems and components are being controlled and accomplished in accordance with NRC >
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| requirements, safety analysis report commitments, and licensee procedure .1 Electrical Installations The following installed electrical systems and components were observed by the inspecto The B Train Emergency Diesel Generator System
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| - 4 Kv Safeguards Switchgear Panels
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| - 480 Volt Safeguards Load Center Panels
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| - Reactor Enclosure Damper Indicator / Control / Test Panel
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| - ATWS 4.16 Kv Switchgear Panel
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| - 125 Volt DC Battery Room 361 The following electrical systems work in progress was observed by the inspector
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| - Replacement of Agastat 7000 series relays in the B Diesel Generator Engine Control Panel with Agastat ETR series relays. This replacement was in response to Information Notices 77-01 and 82-0 ! | |
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| - In place storage / maintenance program for the. emergency diesel generator Observations made by the inspector included the followin The components and panels were properly identifie Protective dust covers were in place over the equipments / panel Protective plywood covers were installed around the bases of panels in heavy ~ construction activity area Electrical space heaters were properly energized in electrical panels-and generator Components were installed in the correct locations with the correct orientatio Electrical separation was maintaine Electrical installation was being performed with approved procedure Where cable had been pulled to panels but not terminated, it was wrapped with protective paper, the ends were taped and it was neatly-coiled to an acceptable radius and secured with tyrap In place storage / maintenance of the diesel generators was in accordance with the manufacturers recommendations and approved licensee procedure No violations were identifie .0 Electric Cable-Work Observation The inspector reviewed activities related to safety related cables for safety related systems to determine if they are controlled and accomplished in accordance with NRC requirements, safety analysis report commitments and license procedures. This included direct observations and an inde-pendant evaluation of work performance, work in progress and completed wor ,
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| 5.1 Storage The following storage /maintanenance attributes of licensee construction procedures CP-E-2 and CP-F-2 were observed by the inspector in the cable receipt / storage / cut yard (Note: All permanent in plant cable is procured to the same "Q" Specification requirements regardless of the application (Q or Non-Q) except for GE furnished "non Q" PGCC cable).
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| - Permanent plant cable and PGCC (Q and Non Q) were stored / maintained in separate areas of the cable yar Master cable reels (as received from the manufacturer) were identified with manufacturer's information and the Bechtel cable code to provide cable identity and traceabilit Sub-master cable reels were provided identity to provide traceability to the master ree Cable ends were sealed with end caps or tap l
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| | Management Assistant, DRMA (w/o enc 1) |
| - Cable reels were stored above the concrete / ground to preclude cable contact with surface water, j
| | Section Chief,'DRP Robert J. Bores, DRSS i |
| - Temporary cable was stored in a remote area with a large letter I
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| "T" painted on the cable reel Licensee procedure CP-F-2 requires that the temperatures of cable on reels be above 10' F for removal of cable. The cable tempera- ;
| | DRS:RI R :Rf jDRS:RI Woodard/mjh Anderson Strosnider 08/89/87 08/05'/87 08/g/87 0FFICIAL RECORD COPY RL LIM 2 87-06 - 0002. , |
| ture upon removal was not currently being recorded. The cable yard foreman stated that when weather is cold, reels of cable are brought inside to warm up prior to cable removal. This is an unresolved item (50-353/87-06-01) pending licensee demonstration of the adequacy of existing controls for cable already pulled and the potential need for additional controls for future cable pull The following cable storage / maintenance attributes were observed by the inspector in the permanent plant pre-cut cable laydown (interim storage) area outside the turbine buildin Pre-cut cable lengths were each uniquely identified by attached labels which included the application information (pull from location to destination) and traceability back to the master reel from which it was pulle Construction procedure CP-E-2 paragraph 5.2.3.22 requires measures to " assure that cable in interim storage pending installations is adequately protected including maintaining the reels in an upright position, preventing cable contact with surface water or ground."
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| Some of the pre-cut cable in the laydown area was found to be on reels and stored in an upright position; however, most of the pre-cut cable was in tied coils. The coils were stored off the ground on wooden pallets. The inspector observed this area daily from May 4-14, 1987. On May 13 the inspector observed a few cable coils (approximately 20) which were not stored on pallets so as to keep the cable off the ground and away from water submersion damage. These cable coils were stored on a plastic sheet. The inspector noted that the plastic sheets were dry and there was no contact of the cables with water. The inspector pointed out to the licensee that at a future time rainwater could pool on the plastic and expose the cables to wate The licensee agreed and took prompt action to place the subject cable coils off the ground on wooden pallet Further, since the cable storage procedure, CP-E-2 paragraph 5.2.3-22 did not specifically address coils of cable off the cable reels the licensee agreed to issue a clarifying memo to this procedure. The licensee's proposed corrective actions in-clude revisions paragraph 5.2.3.22 to the procedure and providing instructions to cable handling personnel in proper storage practices. This is an unresolved item pending licensee development of a procedure to control the temporary storage and protection of coils of cable that are not on cable reels. (50-353/87-06-02)
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| | L :. .. PHILADELPHIA ELECTRIC COMPANY I 2301 M ARKET STREET l P.O. DOX 8699 JUL 141937 1 |
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| | PHILADELPHIA A. PA.19101 |
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| | V6C E PftESIDENT anesasa nime ame as seancee |
| 5.2 Electrical Cable-Installation Recorded installation data for several class IE cable installations was reviewed for conformance with specification 8031-E-1412 and construction procedure CP-E-2. The calculated maximum cable pulling tension and sidewall pressure for the installed cables was compared to the data recorded during the installation. In all cases the actual pull tension and sidewall pressure was determined to be less l than the specified limit The inspector reviewed cable calculations E-587 for cable pull j t package SE.01076. This was a bulk pull of six single conductor 500 s KCMIL and one single conductor 250 KCMIL cables through a five inch PVC conduit from Safeguards Load Center Distribution Panel 20B201 to MCC Panel 20B12 The inspector witnessed a portion of the pull which was from Junction box 2AJ019 elevation 313' to junction box 2AJ020 elevation 299' and then to the cable duct at elevation 269' which led to panel 20B129. The maximum allowable cable pull tension was 2245 pound Calculated expected maximum pull tension was 1486 pounds. However, as a result of the good cable and conduit prelubrication, the pull was made with a maximum of five men pulling by hand. The pull tension was estimated to be not in excess of 500 pounds based upon
| | - United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Subject: USNRC Region 1 Letter Dated June 15, 1987 _ Re: Site Inspection of May 4 to 14, 1987 Inspection Report No. 50-353/87-06 Limerick Generating Station, Unit 2 File: QUAL 1-2-2 (353/87-06) |
| .an average tension per man of 100 pounds per paragraph 2.1.3 of specification E-141 No deficiencies were observed in either the cable pulling procedure, records, calculations or the actual cable pull witnesse .3 Electrical Conduit and Cable Tray Installation The inspector observed installed cable tray and conduit at various locations throughout the plant. Inspections were made of conduits 2CLO46 from Motor Control Center MCC 20B221 to MCC 20B217 and conduit 2CLO47 from Motor Control Center MCC 20B221 to MCC 20B217 and conduit 2CL047 from Motor Control Center MCC 20B217 to RHR pump 2AP21 No deficiencies were observed in the identification, routing, configuration, or seismic supports for these conduit i | | Gentlemen: |
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| | In response to the subject letter regarding the item identified during the subject inspection of construction activities authorized by NRC License N CPPR-107 we transmit herewith the following: |
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| | Attachment I - Response to Appendix A Should you have any questions concerning this item, we would be pleased to discuss them with yo |
| 5.4 Electrical Cable Terminations The inspector observed wire and cable terminations in load centers, l motor control centers, fuse panels, and in control cabinets at !
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| several locations. An inspection was made of licensee cable termi- j nations in Motor Control Centers MCC 20B221 and MCC 20B217 of cable which was installed in accordance with cable schemes CB217-03A and CB217-04A. In addition, an inspection was made of control wire terminations made by licensee in the "B" emergency diesel generator engine control panel. No deficier:cies were observe '
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| . | | Sincerely, |
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| | JMC/pc Attachment Copy to: United States Nuclear Regulatory Commission Office of Inspection & Enforcement, Region 1 631 Park Avenue King of Prussia, PA 19406 R. Gramm, USNRC Resident Inspector |
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| 6.0 Electrical Distribution System 6.1 Adequacy of Electrical Distribution System to Provide Required Voltage Levels to Class IE Equipmen The inspector reviewed the licensee's voltage profile studies and a licensee letter to NRC dated October 22, 1981, in which low voltage problems in certain class IE circuits were identified under Signi-ficant Deficiency Report No. 52 for both Limerick Units #1 and # In this letter the licensee confirmed a previous 50.55(e) telecon to )
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| the NRC in which potential undervoltage conditions for 166 safety j related circuits were reported. Commitments were made by the i licensee to the NRC, in this letter, to complete design changes and installation to correct the affected circuits for Unit 2 by June 3'
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| 198 ll The inspector reviewed the Bechtel " Final Report on Undervoltage Problems in Certain Power And Control Circuits For LGS Unit #1 And Common" dated February 1983 in which corrective actions were detailed to correct a total of 534 deficient circuits for Unit #1 and circuits common to Units 1 and The inspector was unable to locate a record of design changes and installation in Unit 2 to correct the under-voltage deficient circuit This technical item is a construction deficiency outstanding open item (50-353/80-00-12). Failure to meet the Unit 2 June 1986 commitment to NRC is a deviation to their commitmen (50-353/87-06-03)
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| 7.0 Definition of Unresolved Items Unresolved items are matters about which more information 13 required in order to ascertain whether they are acceptable, violations, or deviations relative to the bulletin requirements. Unresolved items identificd ,
| | These commitments are being tracked for closure by Philadelphia Electric and the Nuclear Regulatory Commission on their respective open item lists. The Philadelphia Electric Company maintains its open item list by a process wherein we continuously review and update the list. This will ensure that commitments made as a result of Construction Deficiency Reports, IE Circulars, Bulletins, and Notices, Unit 2 Inspection Reports and any other appropriate documents are me By correlating our open item list with those open items known to exist by our Nuclear Regulatory Commission Resident Inspectors we are confident that a comprehensive list of commitments is maintained and that those commitments will be met in accordance with the present construction schedule I l |
| during this inspection are discussed in paragraphs 5 and 6 abov '
| | JMC/pc I 2/2 7/9/87 353/87-06 |
| 8.0 Exit Meeting The NRC inspector conducted an exit meeting on [[Exit meeting date::May 14, 1987]] with licensee ,
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| representative (denoted in paragraph 1). The NRC inspector summarized the '
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| inspection findings and the licensee acknowledged these comments. No l written material was provided to licensee personne i a
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| Attachment A Documents Reviewed 1.0 Final Safety Analysis Report, Chapter 8 - Electric Power 2.0 Construction Procedures (CP)
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| D-1 Processing of Nonconformence Reports, Rev. 4, 6/26/86 D-7 Construction Administration Control, Rev. 8, 5/20/87 E-1 Electrical Panel Modifications, Rev. 6, 5/20/87 E-2 Permanent Plant Cable Installation and Termination, Rev. 3, 2/2/87 E-3 Electrical Raceway, Rev. 3, 10/15/86 G-3 ' Long Term Storage / Maintenance / Lubrication of Permanent Plant Equipment and Materials Prior to Turnover, Rev. 3, 10/22/86 F-2 Receipt Inspection-Storage and Withdrawal of Materials / Equipment, Rev. 9, 5/18/87 3.0 Drawings E-1412 Wire and Cable Notes and Detail, Rev. 30, 2/4/87 E-1406 Conduit and Cable Tray Notes, Symbols and Details, Rev. 6, 5/6/87 E-1420 Maximum Allowable Cable Length - Power and Control Circuits, Rev.1, 12/14/83 E-66 Single Line Meter and Relay Diagram, MCC Load Tabulation, Rev. 5, 4/26/83 E-159 Load Center SWGR-MCC FDR Bkrs. 440v, Rev. 27, 1/23/87 E-160 Safeguard Buses - 101 and 201, Safeguard Bus Feeders, 4Kv, Rev. 19, 1/3/85 E-162 Safeguard Buses - Load Center Transformer Bkrs. 4Kv, Rev. 6, 12/14/82 E-163 Safeguard Buses - Load Center Transformer Bkrs. 4Kv, Rev. 12, 1/7/85 E-164 Safeguard Buses - Generator Bkrs 4Kv, Rev. 19, 10/18/84 E-1 Single Line Diagram - Station, Rev. 13, 4/26/85 E-16 Single Line Meter and Relay Diagram, 4Kv Safeguard Power System, Rev. 15, 8/1/85 E-29 Single Line Meter and Relay Diagram, 0214, D224, D234, D244, Safeguard Load Centers, 440 volt, Rev. 10, 12/18/85 4.0 Reports
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| - Significant Deficiency Report No. 52 - Undervoltage Condition in Certain Electrical Power and Control Circuits, 10/22/81
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| - Final Report on Undervoltage Problems in Certain Power and Control Circuits for LGS Unit 1 and Common, 2/16/83 l
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| | Attachment I i Response to Appendix A Deviations |
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| . | | On September 24, 1981 the licensee by telephone reported to the NRC a potential 10 CFR 50.55(e) deficiency in the adequacy of the electrical distribution system to provide the required voltage _ |
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| 5.0 Quality Records PECO Audit Reports 2E-230 GE Cable Installation (5/8 - 5/19/86)
| | letter to the NRC dated October 22, 1981 in which the licensee made a commitment to complete both the design changes and installation to correct the affected circuits by June 198 Contrary to the above the licensee has not provided evidence to demonstrate either completion of the design changes required or |
| 2E-245 Diesel Generator Control Panels (12/16 - 12/31/86)
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| 2E-227 Motor Control Center 20B224 (3/25 - 4/2/86)
| | the physical installations to provide for the required' voltage levels to class IE component Response As noted by the deviation, we did not complete the work'by June, 1986.- Our original commitment was based on the project-schedule in 1981. Since then, our schedule has been significantly revise The Pennsylvania Public Utility Commission issued a ruling-in December of 1983 which, in effect, brought about the cessation of construction on the Limerick 2 Projec Based on a subsequent-ruling by the Pennsylvania Public. Utility Commission, construction resumed in February of 198 One of the consequences of this delay is that this and other commitments made to the Nuclear Regulatory Commission prior to the cessation of construction were deferred by approximately two year This commitment and others which where submitted in various documents prior to the Pennsylvania Public Utility Commission ruling were based on the construction schedules in effect at the tim Based on our present schedule, we plan to complete the work associated with the 10 CFR 50.55(e) deficiency in the adequacy of the electrical distribution system by March, 198 In addition, it is our intent to implement the corrective action to resolve all open items. These items will be resolved commensurate with our present construction schedule. As we complete these commitments, it is our intention to present documentary evidence of the resolution of each item to the NRC Regional Inspectors, as we have in the past, in order that each commitment may be close JMC/pc I 1/2 7/9/87 353/87-06 |
| 2E-248 Cable Pulling of PGCC Cables (2/13 - 2/20/87)
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| 2E-225 Material Control (11/13 - 11/20/85)
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| 2E-236 Electrical Cable Storage Program (7/10 - 7/31/86)
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| 2E-180 Control of Electrical Parts and Components (11/13 - 11/20/85)
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| Maintenance Action Records for In Storage Maintenance of "B" Emergency Diesel Generator 6.0 Calculations E-587 Cable Pulling Tension, 4/27/87 E-590 Cable Pulling Tension, 5/4/87 LGS Units 1 and 2 Final Calculations Index EE.350 Bechtel Computer Program Manual for Cable Tension Calculation I J
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D5211999-09-30030 September 1999
Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule
ML20216J3981999-09-29029 September 1999
Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity
ML20212J6561999-09-29029 September 1999
Informs of Completion of mid-cycle PPR of Limerick Generating Station on 990913.Identified No Areas in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl
ML20212H6401999-09-24024 September 1999
Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl
ML20212E7941999-09-22022 September 1999
Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS
ML20212E8081999-09-22022 September 1999
Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74
ML20212F5481999-09-20020 September 1999
Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2
ML20212F8991999-09-17017 September 1999
Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed
05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999
Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl
ML20216F7821999-09-16016 September 1999
Forwards Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Inoperability of Automatic Depression Sys During Maint
ML20212A8751999-09-13013 September 1999
Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief
ML20211N5061999-09-0909 September 1999
Forwards TSs Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS, Units 1 & 2,being Issued to Assure Distribution of Revised Bases Pages to All Holders of TSs
ML20212A0091999-09-0909 September 1999
Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment
ML20211P8571999-09-0808 September 1999
Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812
ML20211P3891999-09-0303 September 1999
Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018
05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999
Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed
ML20211H2571999-08-26026 August 1999
Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed
ML20211E9191999-08-24024 August 1999
Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info
ML20211E9731999-08-23023 August 1999
Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g)
ML20211D6761999-08-20020 August 1999
Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6)
ML20210T4271999-08-13013 August 1999
Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed
ML20210U2211999-08-10010 August 1999
Forwards Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Late Performance of off-gas Grab Sample Surveillance
05000353/LER-1999-005, Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint1999-08-10010 August 1999
Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint
ML20211B7881999-08-10010 August 1999
Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714
ML20210M7571999-08-0404 August 1999
Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response
ML20210P4191999-08-0404 August 1999
Forwards Initial Exam Repts 50-352/99-302 & 50-353/99-302 on 990702-04 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam
NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999
Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls
ML20210L2011999-07-28028 July 1999
Forwards Final Personal Qualification Statement (NRC Form 398) for Reactor Operator License Candidate LB Mchugh
ML20211F2641999-07-27027 July 1999
Forwards Three Copies of Rev 12 to LGS Physical Security Plan, Rev 4 to LGS Training & Qualification Plan & Rev 2 to LGS Safeguards Contingency Plan. Without Encls
05000352/LER-1999-008, Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator1999-07-23023 July 1999
Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator
05000353/LER-1999-004, Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs1999-07-23023 July 1999
Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs
ML20210E6211999-07-22022 July 1999
Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3
ML20216D3081999-07-19019 July 1999
Requests Renewal of OLs for Listed Individuals,Iaw 10CFR55.57.NRC Forms 398 & 396,encl for Applicants.Without Encl
ML20216D8041999-07-19019 July 1999
Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007
05000352/LER-1999-006, Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error1999-07-12012 July 1999
Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error
ML20209F6341999-07-0909 July 1999
Submits Supplemental Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 2.Rev 0 to 1H61R & GE-NE-B13-02010-33NP Repts & Revised Pages to Summary Rept Previously Submitted,Encl
ML20209G9121999-07-0909 July 1999
Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton
ML20209C9041999-07-0808 July 1999
Forwards Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 & Revised Monthly Repts for May 1999
ML20210B4441999-07-0808 July 1999
Forwards Preliminary NRC Form 398 & NRC Form 396 for Reactor Operator for License Candidate LB Mchugh.Candidate Failed Category B Portion of Operating Exam Given at LGS During Week of 990315.Tentative re-exam Has Been Scheduled 990812
05000353/LER-1999-003, Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure1999-07-0707 July 1999
Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure
ML20209D8821999-07-0707 July 1999
Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001
ML20209D2671999-07-0202 July 1999
Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
ML20196J6301999-07-0101 July 1999
Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2
05000352/LER-1999-004, Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys1999-07-0101 July 1999
Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys
ML20209B7001999-06-30030 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants
ML20212J5401999-06-28028 June 1999
Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs. Bulletin Closed for Unit 2 by NRC
ML20207H8271999-06-24024 June 1999
Informs NRC That Util Has Completed Core Shroud Insps for LGS Unit 2.Proprietary Rept GE-NE-B13-02010-33P & non-proprietary Rev 0 to 1H61R,encl.Proprietary Rept Withheld,Per 10CFR2.790(a)(4)
ML20196G7041999-06-24024 June 1999
Forwards Insp Repts 50-352/99-03 & 50-353/99-03 on 990413- 0524.No Violations Noted.Nrc Concluded That Licensee Staff Continued to Operate Both Units Safely
ML20196A5641999-06-15015 June 1999
Provides Info Re Util Use of Four Previously Irradiated LGS, Unit 1,GE11 Assemblies in Unit 2 Cycle 6.Encl 990518 GE Ltr Provides Objective of Lead Use Assemblies Program & Outlines Kinds of Measurements That Will Be Made on Assemblies
ML20195J6831999-06-11011 June 1999
Provides Proprietary Objectives for Lgs,Units 1 & 2,1999 Emergency Preparedness Exercise Scheduled to Be Conducted on 990914.Licensee Identifies Which Individuals Should Receive Copies of Info.Proprietary Info Withheld
1999-09-09
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20062G4531990-11-20020 November 1990
Forwards SE Supporting Util Actions to Address Indication in Reactor Vessel Recirculation Riser nozzle-to-safe End Weld
ML20062G4021990-11-19019 November 1990
Forwards Safety Insp Repts 50-352/90-21 & 50-353/90-20 on 900827-31.No Violations Noted
ML20062F1771990-11-13013 November 1990
Confirms Dates of 901126-30 for NRC Equipment Qualification Insp of Facility
ML20058F1981990-11-0505 November 1990
Advises That 901002 Response to Generic Ltr (GL) 90-03, Relaxation of Staff Position in GL 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable
ML20058E6121990-10-29029 October 1990
Forwards Radiological Safety Insp Repts 50-352/90-24 & 50-353/90-23 on 901001-05.No Violations Noted
ML20058D2371990-10-26026 October 1990
Informs of Impending fitness-for-duty Program Insp & Requests 10CFR26.20 Required Policies & Procedures
ML20058C1331990-10-23023 October 1990
Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 910121 & Requalification Program Evaluation Scheduled for Wks of 910114 & 21.Ref Matl Listed on Encl Should Be Provided by 901029
ML20058A6241990-10-18018 October 1990
Forwards Insp Repts 50-352/90-22 &50-353/90-21 on 900912-19. No Violations Noted
ML20062B7891990-10-12012 October 1990
Forwards Safety Insp Repts 50-352/90-20 & 50-353/90-19 on 900813-0916.No Violations Noted
ML20059N5841990-10-0303 October 1990
Informs That Issuance of Senior Reactor Operator Licenses, for Fuel Handling Only,For More than One Facility Conditionally Acceptable
IR 05000352/19900801990-09-28028 September 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/90-80 & 50-353/90-80.Requests Status of Planned Revs to Procedures & Expected Completion Dates in 910130 Response
ML20059F6561990-08-29029 August 1990
Forwards Notice of Withdrawal of 900516 Application for Amend to License NPF-39,revising Tech Specs to Allow one- Time Extension of Visual Insp Period for Three Small Inaccessible Snubbers in Drywell
ML20058N0531990-08-0606 August 1990
Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum
ML20058M5981990-08-0303 August 1990
Forwards Safety Insp Repts 50-352/90-17 & 50-353/90-16 on 900522-0701 & Notice of Violation.Inspectors Continued to Note Problems W/Procedure Compliance & in Technical Adequacy & Implementation of Procedures
ML20058M3311990-08-0303 August 1990
Forwards Radiological Safety Insp Repts 50-352/90-19 & 50-353/90-18 on 900709-13.No Violations Noted.Weakness Observed in Maint of Station Health Physics Procedures
ML20055E8641990-07-10010 July 1990
Comments on Util 891228 Response to Generic Ltr (GL) 89-10, Safety-Related Motor-Operated Valve (MOV) Testing & Surveillance. Requests Proposed Schedule for Completion of GL Program Along W/Justification for Alternative Schedule
ML20055F5591990-07-0303 July 1990
Forwards Safety Insp Repts 50-352/90-80 & 50-353/90-80 on 900521-25.Plant Transient Response Implementing Plan (Trip) Technically Acceptable.Unresolved Items Noted.Impact of Insp Findings on Peach Bottom Trip Procedures Should Be Reviewed
ML20059M8671990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20058K1961990-05-31031 May 1990
Forwards Results & Conclusions of Regulatory Effectiveness Review on 900507-11.Encl Withheld (Ref 10CFR73.21)
ML20055C3091990-02-14014 February 1990
Forwards Safety Insp Repts 50-352/90-03 & 50-353/90-03 on 900116-19.No Violations Noted
ML20248E7421989-09-27027 September 1989
Forwards Exam Repts 50-352/89-13OL & 50-353/89-22OL Administered on 890612-16 & 19.NRC Concerned About Effectiveness of Util Candidate Screening & Evaluation Process That Permitted Marginal Individual for NRC Exam
ML20248G6601989-09-27027 September 1989
Forwards Operational Readiness Insp Rept 50-353/89-81 on 890730-0804 & Notice of Violation
ML20248E5181989-09-22022 September 1989
Forwards Safety Insp Repts 50-352/89-15 & 50-353/89-24 on 890626-0730.No Violations Noted.Repts Delineate NRC Concerns Identified During mid-cycle SALP Review & Licensee self-assessment of Conduct of Operations
ML20248G9611989-09-21021 September 1989
Forwards Amend 7 to Indemnity Agreement B-101,reflecting Increase in Primary Layer of Liability Insurance.Amends Conform to Changes Made to Price-Anderson Act Enacted on 880820
NUREG-1376, Forwards Tech Specs,NUREG-1376 & Sser 9 Re Application for OL for Facility.W/O Encls1989-09-11011 September 1989
Forwards Tech Specs,NUREG-1376 & Sser 9 Re Application for OL for Facility.W/O Encls
ML20247N2331989-09-0808 September 1989
Forwards Insp Repts 50-352/89-17 & 50-353/89-25 on 890724-27.No Violations Noted.Corrective Actions Re Failure of Operators to Properly Classify Events Effective
ML20247E7991989-09-0606 September 1989
Forwards Safety Insp Rept 50-352/89-16 on 890807-11.No Violations Noted
ML20246D5641989-08-23023 August 1989
Forwards Corrective Action Insp Rept 50-353/89-201 During Wk of 890424 Re Independent Design Assessment.Assessment Provided Needed Addl Assurance That Plant Design Met Licensing Commitments
ML20246N4111989-08-15015 August 1989
Forwards FEMA Rept on 890614 Plant Remedial Exercise.Rept Indicates That Deficiency Identified in Lower Pottsgrove Township During 880405 full-participation Exercise.Offsite Preparedness Adequate
ML20245K0161989-08-11011 August 1989
Advises That 890403 Response to Generic Ltr 83-28,Item 2.1 Parts 1 & 2 Acceptable
ML20245G1511989-08-10010 August 1989
Discusses Emergency Preparedness Insp Repts 50-352/89-11 & 50-353/89-17 on 890522-26 & 0607 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of 75,000
ML20245J8171989-08-0909 August 1989
Advises That Listed Schedule Should Be Used for All Emergency Exercises,Including Submittal & Review of Objectives & Scenario Packages Prior to Exercise
ML20245H7151989-08-0909 August 1989
Discusses Insp Rept 50-352/89-14 on 890629 & Forwards Notice of Violation.Insp Reviewed Circumstances Involving Transport of Contaminated Waste from Unit to Quadrex Recycle Ctr in Oak Ridge,Tn on 890620
ML20245G6721989-08-0808 August 1989
Forwards Environ Assessment & Finding of No Significant Impact Re Request for Exemption from 10CFR50.44(c)(3)(i) to Extend Permitted Time of Operation W/Noninerted Containment Until Completion of 100 H Warranty Run
ML20248C3571989-07-31031 July 1989
Forwards Request for Addl Info Re Consideration of Severe Accident Mitigation Design Alternatives.Response Requested within 30 Days of Ltr Receipt
ML20248D8901989-07-28028 July 1989
Forwards Safety Insp Repts 50-352/89-12 & 50-353/89-19 on 890529-0625 & Notice of Violation.Fire Protection Issues, Discussed in Section 3.1,may Represent Potential Enforcement Issues
ML20247N4761989-07-25025 July 1989
Forwards Enforcement Conference Rept 50-352/89-14 on 890717. Apparent Violation Noted in Insp Rept 50-352/89-14 Re Area of Transportation of Radioactive Matl Discussed
NUREG-1371, Forwards Tech Specs,NUREG-1371,issued by NRR Re Application for Ol.W/O Stated Encl1989-07-25025 July 1989
Forwards Tech Specs,NUREG-1371,issued by NRR Re Application for Ol.W/O Stated Encl
ML20246N1801989-07-13013 July 1989
Forwards Preoperational Insp Rept 50-353/89-20 on 890530- 0621.Programs Adequate to Support Testing & Startup
ML20246N4171989-07-12012 July 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/89-80 & 50-353/89-80
ML20246K5461989-07-11011 July 1989
Forwards Reactive Safety Insp Rept 50-352/89-14 on 890629. Violations Noted.Concern Expressed Re Lack of Control in Area of Properly Packaging Matl to Ensure External Radiation Levels Mantained.Enforcement Conference Scheduled
ML20246G2921989-07-0707 July 1989
Forwards Safety Insp Rept 50-353/89-21 on 890530-0602.No Violations Noted
ML20246F5911989-07-0606 July 1989
Forwards to Ecology Ctr of Southern California Re Petition to Fix or Close All Nuclear Power Reactors Designed by Ge.Ltr Ack Receipt of Petition Filed by Ecology Ctr & States Petition Filed Under 10CFR2.206
NUREG-1360, Forwards Tech Specs,NUREG-1360 & Sser 8 Re Application for OL for Unit 2.W/o Encl1989-07-0303 July 1989
Forwards Tech Specs,NUREG-1360 & Sser 8 Re Application for OL for Unit 2.W/o Encl
ML20246B6061989-06-27027 June 1989
Ack Receipt of Re Alleged Discrimination Against Employee for Engaging in Protected Activities.Nrc Considers Matter Closed by Review of Info
ML20245F0401989-06-22022 June 1989
Forwards License NPF-83 Authorizing Fuel Loading & Precriticality Testing of Util & Fr Notice.Amend 4 to Indemnity Agreement B-101 Also Encl
ML20245H6901989-06-21021 June 1989
Forwards Safety Insp Repts 50-352/89-11 & 50-353/89-17 on 890522-26 & 0607.Violations Noted.Enforcement Conference Will Be Held on 890705 to Discuss Operators Inability to Properly Classify Certain Events During walk-through Exams
ML20245F2941989-06-20020 June 1989
Approves Util 880621 Power Ascension Test Program for Facility,Per Reg Guide 1.68,for Execution
ML20245E6141989-06-20020 June 1989
Forwards SER Accepting Util 890331 & 0602 Responses to NRC Bulletin 88-005, Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co at Williamstown,Nj
ML20245F2991989-06-16016 June 1989
Forwards Safety Insp Rept 50-353/89-23 on 890605-07.No Violations or Deviations Noted
1990-09-28
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212J6561999-09-29029 September 1999
Informs of Completion of mid-cycle PPR of Limerick Generating Station on 990913.Identified No Areas in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl
ML20216F7821999-09-16016 September 1999
Forwards Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Inoperability of Automatic Depression Sys During Maint
ML20212A8751999-09-13013 September 1999
Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief
ML20211N5061999-09-0909 September 1999
Forwards TSs Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS, Units 1 & 2,being Issued to Assure Distribution of Revised Bases Pages to All Holders of TSs
ML20211P8571999-09-0808 September 1999
Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812
ML20211P3891999-09-0303 September 1999
Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018
ML20211H2571999-08-26026 August 1999
Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed
ML20210T4271999-08-13013 August 1999
Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed
ML20211B7881999-08-10010 August 1999
Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714
ML20210U2211999-08-10010 August 1999
Forwards Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Late Performance of off-gas Grab Sample Surveillance
ML20210P4191999-08-0404 August 1999
Forwards Initial Exam Repts 50-352/99-302 & 50-353/99-302 on 990702-04 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam
NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999
Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls
ML20196J6301999-07-0101 July 1999
Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2
ML20212J5401999-06-28028 June 1999
Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs. Bulletin Closed for Unit 2 by NRC
ML20196G7041999-06-24024 June 1999
Forwards Insp Repts 50-352/99-03 & 50-353/99-03 on 990413- 0524.No Violations Noted.Nrc Concluded That Licensee Staff Continued to Operate Both Units Safely
ML20206Q5871999-05-14014 May 1999
Advises That Info Contained in ,Which Submitted Revised Procedures for Plant EP Response Procedures Will Be Withheld from Public Disclosure,Per 10CFR2.790(a)(6)
ML20206R3031999-05-11011 May 1999
Informs That on 990407,NRC Administered GFE Section of Written Operator Licensing Exam to Employees of Facility. Forwards Copies of Both Forms of Exam,Including Answer Keys & Grading Results of Facility
ML20206N1111999-05-0707 May 1999
Forwards Insp Repts 50-352/99-02 & 50-353/99-02 on 990302-0412.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy
ML20206H2651999-05-0606 May 1999
Informs That on 990112 Licensee Submitted to NRC Core Shroud Insp Plan for Plant,Unit 2,in Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors
ML20206G5131999-05-0303 May 1999
Approves Change of Completion Date for Implementation of Thermo-Lag Fire Barrier Corrective Actions at Plant from End of April 1999 Limerick Unit 2 RFO to 990930
ML20206H8301999-04-30030 April 1999
Forwards Exam Repts 50-352/99-301 & 50-353/99-301 on 990312-19 (Administration) & 22-26 (Grading).Four of Five RO Applicants & Three of Four SRO Applicants Passed All Portions of Exams
ML20206E6951999-04-30030 April 1999
Advises That Plant,Unit 2 Cycle 6 Safety Limit Mcpr, ,contained in PECO Energy Co 990311 Application & 990204 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790
ML20206F4221999-04-27027 April 1999
Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990312 & 990315-19 at Facility.Completed ES-501-2,power Plant Licensing Exam Results Summary & Summary of Overall Exam Results Encl.Without Encl
ML20205N2291999-04-0909 April 1999
Discusses Limerick Generating Station Plant Performance Review Conducted for Period April 1998 Through 990115 & Informs of NRC Planned Insp Effort Resulting from Review. Historial Listing of Plant Issues,Encl
IR 05000352/19980091999-03-30030 March 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-09 & 50-353/98-09 Issued on 990106.Actions Will Be Examined During Future Insp of Licensed Program
ML20205C2711999-03-26026 March 1999
Forwards Insp Repts 50-352/99-01 & 50-353/99-01 on 990112-0301.One Violation Noted & Being Treated as Non-Cited Violation.Staff Conduct of Activities During Insp Generally Characterized by Safe & Conservative Decision Making
ML20205G7651999-03-22022 March 1999
Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant, Units 1 & 2.Response Requested within 90 Days of Receipt of Ltr
ML20204G9721999-03-11011 March 1999
Informs of Completion of Review of Changes Proposed by PECO Energy Co to Lgs,Units 1 & 2,EALs.Proposed EALs Incorporate Guidance in NUMARC/NESP-007,Rev 2.Forwards Safety Evaluation Supporting Proposed Changes
ML20204H8171999-03-10010 March 1999
Discusses Request That NEDC-32645P, Limerick Generating Station,Units 1 & 2,SRV Setpoint Tolerance Relaxation Licensing Rept, Rev 2,dtd Dec 1998,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld
ML20207J0611999-03-0808 March 1999
Provides Authorization to Administer Initial Written Exams to Listed Applicants on 990312.NRC Region I Operator Licensing Staff Will Administer Operating Tests on 990315-19 at Limerick Generating Station
ML20203G6721999-02-17017 February 1999
Second Partial Response to FOIA Request for Documents. Records in App D Encl & Being Made Available in Pdr.App E Records Being Withheld in Part (Ref FOIA Exemption 5) & App F Records Completely Withheld (Ref FOIA Exemptions 6 & 7)
ML20203B9001999-02-0808 February 1999
First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6)
ML20202J0261999-02-0303 February 1999
Informs of Completion of Licensing Action for NRC Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors
ML20203A6111999-01-22022 January 1999
Confirms 990115 Conversation Between Mj Williams & P Orphanos Re Arrangements Made for Administration of Licensing Exam at Limerrick Generating Station & Peach Bottom Atomic Power Station During Week of 990705
ML20199F9251999-01-11011 January 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-05 & 50-353/98-05
ML20199C6501999-01-0606 January 1999
Forwards Insp Repts 50-352/98-09 & 50-353/98-09 on 981018- 1130 & Notice of Violation.Violation of Concern Because Technicians Exercised Poor Judgement & Deviated from Procedure in Attempt to Resolve Problem Without Mgt
ML20198H4951998-12-18018 December 1998
Forwards Results of Audit of Licensee Year 2000 Program for Limerick Generating Station,Units 1 & 2
ML20198A3721998-12-10010 December 1998
Forwards Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves
ML20198B1751998-12-0808 December 1998
Advises of Planned Insp Effort Resulting from Limerick mid-year Insp Resource Planning Meeting Held on 981110. Historical Listing of Plant Issues & Details of Insp Plan for Next Six Months Encl
IR 05000352/19980081998-11-23023 November 1998
Discusses licensee-identified Issue Involving Potential for Bypass of Suppression Pool as Documented in Insp Repts 50-352/98-08 & 50-353/98-08.NOV Will Not Be Issued & Civil Penalty Will Not Be Proposed
ML20196C3311998-11-23023 November 1998
Forwards Insp Repts 50-352/98-08 & 50-353/98-08 on 980901-1017.No Violation Identified.Security Program Insp Identified That Security Program Effectively Protects Public Health & Safety
ML20195D1491998-11-13013 November 1998
Forwards RAI Re on-going Review of IPEEE Submittal Dtd 951014.Understands That Licensee Will Inform NRC in Writing, by 981130,on How Question Re Effects of New Probable Max Precipitation at Plant,Units 2 & 3 Will Be Addressed
IR 05000352/19980061998-10-15015 October 1998
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-06 & 50-353/98-06 on 980826.Finds C/As for Violation Involving Failure to Select Performance Measures to Be Acceptable
ML20154F8191998-10-0101 October 1998
Forwards Notice of Withdrawal of 960503 & Suppl Application for Amend to Fols.Amend Would Have Modified Facility TSs Pertaining to Rev to Frequency of Testing Stand Gas Treatment Sys & Reactor Encl Recirculation Sys
ML20154A3461998-09-25025 September 1998
Forwards Insp Repts 50-352/98-07 & 50-353/98-07 on 980707-0831.No Violations Noted.Weaknesses Noted with Reactor Engineering Support to Rod Pattern Adjustment
ML20153G4291998-09-24024 September 1998
Forwards Request for Addl Info Re Licensee Revised Emergency Action Level Guidelines for Limerick Generating Station, Units 1 & 2 & Peach Bottom Atomic Power Station,Units 2 & 3. Response Requested within 30 Days of Receipt of Ltr
ML20153D0151998-09-21021 September 1998
Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Plant, Units 1 & 2
ML20151X2421998-09-11011 September 1998
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-04 & 50-353/98-04 on 980805
ML20151W9601998-09-10010 September 1998
Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Were Selected as SRAs for Region I
ML20237D5421998-08-26026 August 1998
Ack Receipt of & Fee for $55,000 in Payment for Civil Penalty Proposed by NRC in .C/As Will Be Examined During Future Insps
1999-09-09
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. I AUG 0 51987 i Docket N Philadelphia Electric Company ATTN: Mr. John S. Kemper Senior Vice President Engineering and Production 2301 Market Street Philadelphia, PA 19101 Gentlemen:
Subject: Inspection No. 50-353/87-06 This refers to your letter dated July 14, 1987, in response to our letter dated June 15, 198 Thank you for informing us of the corrective and preventive actions cocumented in your letter. These actions will be examined during a future inspectio Your cooperation with us is appreciate
Sincerely, j
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Ori 8inal Signed B 3 j
William V. Johnston, Director l
, Division Reactor Safety cc w/ encl:
S. J. Kowalski, Vice President, Engineering and Research W. T. Ullrich, Superintendent, Limerick 2 Project j J. M. Corcoran, Quality Assurance Manager Troy B. Conner, Jr. , Esquire Eugene J. Bradley, Esquire, Assistant General Counsel Public Document Room (PDR)
Local Public Document Room (LPDR) l Nuclear Safety Information Center (NSIC) .
NRC Resident Inspector -
Commonwealth of Pennsylvania i
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B708120239 B70B05 PDR ADOCK 05000353 0 PDR OFFICIAL RECORD COPY RL LIM 2 87-06 - 0001. /05/87 i
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Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o enc 1)
Section Chief,'DRP Robert J. Bores, DRSS i
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DRS:RI R :Rf jDRS:RI Woodard/mjh Anderson Strosnider 08/89/87 08/05'/87 08/g/87 0FFICIAL RECORD COPY RL LIM 2 87-06 - 0002. ,
08/02/87
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L :. .. PHILADELPHIA ELECTRIC COMPANY I 2301 M ARKET STREET l P.O. DOX 8699 JUL 141937 1
PHILADELPHIA A. PA.19101
. S. J. KOWALSKI
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V6C E PftESIDENT anesasa nime ame as seancee
- United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Subject: USNRC Region 1 Letter Dated June 15, 1987 _ Re: Site Inspection of May 4 to 14, 1987 Inspection Report No. 50-353/87-06 Limerick Generating Station, Unit 2 File: QUAL 1-2-2 (353/87-06)
Gentlemen:
In response to the subject letter regarding the item identified during the subject inspection of construction activities authorized by NRC License N CPPR-107 we transmit herewith the following:
Attachment I - Response to Appendix A Should you have any questions concerning this item, we would be pleased to discuss them with yo
Sincerely,
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JMC/pc Attachment Copy to: United States Nuclear Regulatory Commission Office of Inspection & Enforcement, Region 1 631 Park Avenue King of Prussia, PA 19406 R. Gramm, USNRC Resident Inspector
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These commitments are being tracked for closure by Philadelphia Electric and the Nuclear Regulatory Commission on their respective open item lists. The Philadelphia Electric Company maintains its open item list by a process wherein we continuously review and update the list. This will ensure that commitments made as a result of Construction Deficiency Reports, IE Circulars, Bulletins, and Notices, Unit 2 Inspection Reports and any other appropriate documents are me By correlating our open item list with those open items known to exist by our Nuclear Regulatory Commission Resident Inspectors we are confident that a comprehensive list of commitments is maintained and that those commitments will be met in accordance with the present construction schedule I l
JMC/pc I 2/2 7/9/87 353/87-06
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Attachment I i Response to Appendix A Deviations
On September 24, 1981 the licensee by telephone reported to the NRC a potential 10 CFR 50.55(e) deficiency in the adequacy of the electrical distribution system to provide the required voltage _
levels to some class IE circuits. The report was confirmed by
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letter to the NRC dated October 22, 1981 in which the licensee made a commitment to complete both the design changes and installation to correct the affected circuits by June 198 Contrary to the above the licensee has not provided evidence to demonstrate either completion of the design changes required or
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the physical installations to provide for the required' voltage levels to class IE component Response As noted by the deviation, we did not complete the work'by June, 1986.- Our original commitment was based on the project-schedule in 1981. Since then, our schedule has been significantly revise The Pennsylvania Public Utility Commission issued a ruling-in December of 1983 which, in effect, brought about the cessation of construction on the Limerick 2 Projec Based on a subsequent-ruling by the Pennsylvania Public. Utility Commission, construction resumed in February of 198 One of the consequences of this delay is that this and other commitments made to the Nuclear Regulatory Commission prior to the cessation of construction were deferred by approximately two year This commitment and others which where submitted in various documents prior to the Pennsylvania Public Utility Commission ruling were based on the construction schedules in effect at the tim Based on our present schedule, we plan to complete the work associated with the 10 CFR 50.55(e) deficiency in the adequacy of the electrical distribution system by March, 198 In addition, it is our intent to implement the corrective action to resolve all open items. These items will be resolved commensurate with our present construction schedule. As we complete these commitments, it is our intention to present documentary evidence of the resolution of each item to the NRC Regional Inspectors, as we have in the past, in order that each commitment may be close JMC/pc I 1/2 7/9/87 353/87-06
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