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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20210Q9991997-08-28028 August 1997 Safety Evaluation Concluding That Since 25th Tendon Surveillance on Few Yrs Away,Adequacy of Remaining Prestressing Force Will Be Critical to Verify ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20138H6671996-12-19019 December 1996 Safety Evaluation Accepting Util IPE Submittal in Response to GL 88-20 ML20134D7811996-10-24024 October 1996 Safety Evaluation Supporting Amend 51 to License DPR-73 ML20128L6741996-10-11011 October 1996 Safety Evaluation Accepting Third ten-year Interval for Pump & Valve Inservice Testing Program for Facility ML20128K1981996-10-0808 October 1996 Safety Evaluation Supporting Amend 50 to License DPR-73 ML20059D1771993-12-28028 December 1993 Safety Evaluation Supporting Amend 48 to License DPR-73 ML20062K1041993-12-0606 December 1993 Safety Evaluation Supporting Amend 47 to License DPR-73 ML20058F0311993-11-16016 November 1993 SE Informing That Changes to Pdms Requirements & Commitments List of 930115,does Not Constitute Unreviewed Safety Question,Nor Do They Involve Significant Hazard or an Environmental Impact ML20059K3001993-11-0808 November 1993 Safety Evaluation Supporting Amend 46 to License DPR-73 ML20057A3641993-09-0101 September 1993 SER Denying Licensee 930216 & 0416 Requests for Relief from Certain Requirements of ISI Program ML20056F0171993-08-0505 August 1993 Safety Evaluation Accepting Proposed Changes to Pdms Requirements & Commitments List of 930115 ML20128P7321993-02-19019 February 1993 Safety Evaluation Supporting Amend 171 to License DPR-50 ML20126M2861993-01-0505 January 1993 Safety Evaluation Granting Relief from ISI Post Repair Hydrostatic Schedule Requirements ML20058G1331990-11-0606 November 1990 Safety Evaluation Supporting Amend 39 to License DPR-73 ML20058P4681990-08-0909 August 1990 Safety Evaluation Accepting Changes to Table 4.3-3 of Recovery Operations Plan ML20247L0681989-09-11011 September 1989 Safety Evaluation Supporting Amend 35 to License DPR-73 ML20245J4411989-06-23023 June 1989 Safety Evaluation Supporting Util 850823 Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Reliability - On-Line Functional Testing of Reactor Trip Sys ML20247E8141989-05-18018 May 1989 Safety Evaluation Accepting Proposed Changes to Recovery Operations Plan ML20247G4131989-05-15015 May 1989 Safety Evaluation Supporting Amend 34 to License DPR-73 ML20245J1201989-04-27027 April 1989 Safety Evaluation Supporting Amend 149 to License DPR-50 ML20245A6521989-04-12012 April 1989 Safety Evaluation Supporting Amend 33 to License DPR-73 ML20196B3071988-12-0101 December 1988 Safety Evaluation Supporting Approval of Lower Core Support Assembly & Lower Head Defueling ML20153E6861988-08-31031 August 1988 Safety Evaluation Accepting Request for Exemption from Lecture Requirements of 10CFR55.59(c)(2) & for Exceptions to Control Manipulations Required by 10CFR55.59(c)(3)(i), Subsections (a) to (AA) ML20153E8471988-08-30030 August 1988 Safety Evaluation Approving Request for Mod of Recovery Operations Plan Table 4.3.3 ML20195B6991988-05-27027 May 1988 Safety Evaluation Supporting Amend 30 to License DPR-73 ML20155B3151988-05-25025 May 1988 Safety Evaluation Supporting Amend 30 to License DPR-73 ML20151D5611988-03-31031 March 1988 Sser of Util 870917 & 1103 Justifications for Proposals & & Relief Requests Re Pump & Valve Inservice Testing Program Denied in 870319 Ser.Exclusion of Stated Valves Accepted ML20150D5101988-03-18018 March 1988 Safety Evaluation Supporting Util 871027 Submittal Re Reconfiguring Main Steam Line Rupture Detection Sys Bypass Indicating Lamp During Cycle 8 Refueling Outage ML20147D9721988-02-26026 February 1988 Supplemental Safety Evaluation Supporting Util Use of Rochester Instrument Sys Model SC-1302 Isolation Devices,Per NUREG-0737,Suppl 1 ML20147E2491988-01-0808 January 1988 Safety Evaluation Supporting Util 871203 & 28 Requests to Use Core Bore Machine to Dismantle Lower Core Suport Assembly ML20237B1501987-12-10010 December 1987 SER Supporting Util Response to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Programs (Reactor Trip Sys Components) ML20236T5611987-11-18018 November 1987 SER Accepting Util 831108,850805 & 870529 Responses to Generic Ltr 83-28,Item 2.2.1, Equipment Classification Programs for All Safety-Related Components ML20236M9221987-11-0505 November 1987 Safety Evaluation Supporting Util Proposal Re Elimination of Postulated Primary Loop Pipe Ruptures from Design Basis ML20235S3241987-10-0101 October 1987 Safety Evaluation Approving Util 870724 Request for Staging of Two Radwaste Solidification Liners in Waste Handling & Packaging facility.TMI-2 Svc List Encl ML20237G5301987-08-12012 August 1987 Safety Evaluation of Util Response to Item 2.1 (Part 1) of Generic Ltr 83-28, Equipment Classification (Reactor Trip Sys Components) TMI-1. Util Response Acceptable ML20234B9701987-06-25025 June 1987 Safety Evaluation Supporting Amend 28 to License DPR-73 ML20212Q7341987-04-17017 April 1987 Safety Evaluation Supporting Amend 27 to License DPR-73 ML20206B4131987-04-0303 April 1987 Safety Evaluation Supporting Util 850416 Request for Deletion of Constraint of 20-ft Square Modified Penetrations Between Reactor & Auxiliary/Fuel Handling Bldgs.Expanding of Limit to 40-ft Square Acceptable ML20205C6161987-03-20020 March 1987 Safety Evaluation Re Util 860820 & 1020 Requests for Relief from ASME Code Section XI Requirements for Class 1,2 & 3 Components.Relief Should Be Granted Except for Requests 4 & 7.Insufficient Info Provided for Request 7 1999-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
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[, p c g UNITED STATES y , 3 y, c g NUCLEAR REGULATORY COMMISSION
- - 1 E WASHINGTON. D. C. 20555
\...../ SAFETY EVALUATION RY THE OFFTCE Or NUCLEAR PEACTCP PEGULATION PUMP ANP VALVE INSERVICE TESTING PROGRAM METPOPOLITAN EDTSON COMPANY JEPSEY CENTPAL POWER AND LIGHT COMPANY PENNSYLVAFTA ELECTRIC COMPANY GPU NUCLEAP CCRFORATION THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 DOCKET NO. 50-289 INTRODUCTION An Inservice Testing (IST) Progran for pumps and valves is reouired by the provisicrs of 10 CFR 50.E5afq) to be revised every 120 months. The IST interval for the first ten years of Three Mile island Unit 1 (TMi-11 operation ended in September 1984 and was evaluated by NRC letter to GPUN dated October 23, 1984 In accordance with NRC regulations, GPUN submitted, on July 10, 1984, an updated IST Program for the second ten-year interval runninc from September 1984 until September 1994 This submittal was intended to follow ASME Boiler and Pressure Vessel Code,Section XI, Division I,1980 Edition and Addenda through Winter 1980, except for a number of specific requests for relief from Code testing requirements.
After a preliminary review, the NRC staff had notified GPUN hv letter dated December 11, 1984, that the updated IST Procram should be implemented pending completion of a detailed staff review. However, the staff did reaffirm denial of several GPUN requests for relief from Code requirements that were previously denied for the first ten-year interval. On May 3,1986, GPI'N submitted a supplement to their proposed IST Program for the second ten-year interval which provided additional information and commitments in response to NRC guidance. The NRC staff subsequently issued a Safety Evaluation (SE) dated October 3, 1986, which concluded that the updated TMI-1 Pump and Valve IST Program (as supplemented) was acceptable with the exception of certain requests for relief which were denied.
A technical meeting was held between GPUN and the staff on October ?7, 1906, to discuss the outstanding open items identified in Appendix D of the SE dated October 3, 1986, as well as denied relief requests. In response to this meeting, GPUN submitted, On December 24, 1986, a supplement to the IST Procran.
Followine a preliminary review of this supplement, the staff conducted a conference call with GPUN and EGAG Idaho (an NRC contractor) on January 15, 1987 to further discuss SE open items. As a result, GPUN submitted a letter dated February 19, 1967, which provided additional information and commitments necessary to resolve NRC staff concerns. In a telephone conference call on Parch 17, 1987, the licensee made further commitments to include certain diesel penerator support syster valves in the IST Program. Finally, by letter dated Parch 13, 1987, GPUF committed to a schedule to resolve the remaining open items under review.
0703300048 G70319 PDR ADOCK 05000209 P PDR
EVAll!ATION Attached is a Supplemental Technical Evaluation Report (TER) for the TMi-1 IST Prooram for Pumps and Valves. The TER was prepared by EGtG Idaho, Inc..
under contract to the NPC. With the exception of items discussed below, the TER is approved by the NRC staff and becomes the NRC staff positicn on the various items discussed. Exceptions and/or further explanation of various sections of the TEP are provided as follows:
- 1. TEP Items 2.2.1 and 2.10.1, Boric Acid Pumps CA-PI A/P and Roric Acid Recycle Purps WDL-P13 A/B By letters dated February 19, 1987 and March 13, 1987, GPUN has aoreed to perform plant modifications necessary to perform cuarterly testing of these pumps, includino the measurement of flow rate in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (i.e. , the Code).
The licensee has requested relief from performing this testino until such time that the plant modifications are installed. After negotiations between GPUN and the NRC, which considered the total Integrated Livino Schedule for plant modifications, the NRC staff accepts the licensee's commitment to complete the modifications prior to startup from the 8R refueling outage. Interim relief from performing the cuarterly testing is granted until the modifications are complete. In the interim, the licensee's current program which tests the pumps each refuelino interval is acceptable.
- 2. TER Appendix D, iten D.1.20, Spent Fuel Coolino System Valves Because of the importance of the Spent Fuel Coolino System in mitigating certain accidents, the staff has continued to require that the valves in this system be included in the IST Program and tested to the requirements of the Code since the licensee does not have a safety-grade source of makeup water to the pool. The licensee has already included the system pumps in previous IST submittals. The licensee has agreed, by letter dated February 19, 1987, to include the recuired Spent Fuel Coolino System valves in the IST Prrgram for testing. The licensee has stated that procedural changes necessary to commence testing of these valves will be implemented prior to six months after February 19, 1987. The staff finds this acceptable since this will provide for the first testing in August 1987, or approximately three months (the Code required testing frequency) after startup for the next fuel cycle. Therefore, interim relief is oranted from testino these valves until the end of August 1987.
- 3. TER Appendix D. Item D.1.23, Diesel Generator Fuel Dil Transfer Pumps and Valves and Diesel Generator Air Start Valves Because of the importance of these diesel generator auxiliary systems to the operation of the diesel generators, the staff has continued to require that the system pumps and valves he included in the IST Procram and tested to the reouirements of the Code. The staff has specifically required that flow rate measurement capability be installed for these pumps in order to assess hydraulic performance. The licensee has agreed, by letters dated February 19, 1987 and March 13, 1987, to install
flow rate instrumentation or tanx level indication to measure flow rate during . quarterly tests of these pumps. The licensee has reouested relief from the Code requirements to measure ' differential pressure, inlet pressure, and testing for a five trinute run time. Further, the licensee reouests relief from reasurinc flow rate until such tire that the necessary modifications are installed.
The staff grants relief fron measuring differential pressure and inlet pressure since these ray be calculated based on fluid levels, and grants relief fren testing for a five minute run time. Because of the particular design of these pumps, relief is also granted from the measurement of lubricant level and vibration. The staff also aorees that relief should be granted from performing flow rate measurement until such tine that necessary modifications are installed. After negotiations between the NRC and GPUN, which considered the total Irtegrated Living Schedule of TMi-1
- plant modifications, the NRC staff accepts a commitment from GPUN to complete these modifications prior to startup from 7R refueling outage.
Until the rodifications are complete, interim relief is granted from performing the flow rate measurement.
The licensee's February 19, 1987 letter did not provide information regarding the testing of Diesel Generator Fuel Oil Transfer valves or the Air Start valves from the air receivers to the solenoid air start valves.
A conference call was conducted March 12, 1987 to resolve this issue.
For the Diesel Generator Fuel Oil Transfer systen, a total of six check valves must be added to the IST Prooram. Specifically, valves DF-V-?3-A/B. DF-V7-A/A, DF-V7-R/A, DF-V7-A/B, and DF-V7-B/P are to be added to the program. However, testing of these check valves is integral to the flow rate measurement discussed above. The licensee has agreed to add these six valves to the IST Prooram when the modifications for flow rate measurement are completed (i.e'., prior to startup from the 7R refueling outage). This is acceptable to the NPC staff. Interim relief is granted from testing these valves until the modifications are complete.
For the Diesel Generator Air Start system, a potential of two valves (EG-V17-A/P) must be added to the IST Program. In the conference call of Parch IP, 1987, GPUN agreed to add these valves to the IST Procram within six months of the date of this SE. Hnwever, if within that six-month period, GPUN determines that failure of these two valves would not cause degradation of diesel generator performance, a letter will be sent to the NRC justi#yino that the valves should not be included in the IST Prooram.
Additionally, GPUH may determine a need for specific relief recuests from certain tests on these valves. If such a need for relief is determined, the relief renuest should be submitted during this six-month period.
Interin relief from performing IST on these two valves is oranted for the six-month period starting from the date o' this SE.
4 TER Item D.1.19, PORV Testing The licensee has agreed to test the P0FV at a frequency and with a rethod which is acceptable to the NPC staff. There is a point nf disagreement between GPUN and the FRC on what category the PORV valve should be classified. GPUN prefers to classify it as a Category C valve. The fRC staff believes it should be more appropriately classified a Category B valve.- However, the valve does not clearly fit either catecory, so there is ronm for disagreement. Nevertheless, the actual testing committed to by GPUN is more restrictive than the testing required for either Category P or C. So the actual classification of the valve is somewhat moot. But, if in the future the generic testing done for Category B valves becomes nore restrictive than the actual testing done at TMI-1 and GPUN elects not to change the PORV testing, the licensee is requested to justify this decision in a letter to the NRC.
- 5. Implementation Schedules The licensee requested clarification of implementation schedules for reliefs approved by our October 3,1986 SE. Specifically, our SE stated that testino for the Control Building Chilled Water pumps (AH-P2/A/B) and the Screen House Ventilation Equipment pump (SV-PP A/B) would require plant modifications to be completed durino the 7R refuelinc outace. Apparently, the wording of the NRC SE left some confusion on whether the schedule for the modifications was acceptable. The TEP attempts to rectify this problem. But to clear up any confusion which may exist, where physical modifications have to be completed prior to doing testing and the NRC has accepted the licensee's modification schedule, interim relief is granted until the physical modifications are complete. The schedule for these modifications for the 7R refueline outage is acceptable to the NRC.
The licensee has made a series of commitments to add components to the IST Program which only reouire the development of testing procedures.
The licensee has conmitted to develop and irplement these procedures within six months of the commitment letter date (specifically GPUN letters dated December P4.1986 and February 19,1987). This schedule is acceptable to the NRC, and interim relief is granted for these corponents until the procedures are implemented.
CONCLUSION The licensee's IST program for the second ten-year interval as described in this SE and its attached TER is acceptable.
Dated: March 19, 1987 Principal Contributors:
Gary Hammer John Thoma Thierry Ross