Proposed Change to Rev 1 to Safety Evaluation 1959, Establishing Controlled Leak in RHR Sys Per Temporary Mod 86-20ML20204F753 |
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Site: |
Pilgrim |
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Issue date: |
06/13/1986 |
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From: |
BOSTON EDISON CO. |
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To: |
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Shared Package |
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ML20204F710 |
List: |
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References |
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1959, 1959-R01, 1959-R1, NUDOCS 8608040299 |
Download: ML20204F753 (10) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20207J5471999-03-0909 March 1999 Training Simulator,1999 4-Yr Certification Rept ML20207B7601998-03-31031 March 1998 Final Rept, Pilgrim Nuclear Power Station Site-Specific Offsite Radiological Emergency Preparedenss Prompt Alert & Notification System Quality Assurance Verification, Prepared for FEMA ML20137C5341997-03-18018 March 1997 Evaluation of Indications Detected in Annulus Core Spray Piping at Pilgrim Nuclear Station ML20137C5471997-03-18018 March 1997 Rev 1 to GE-NE-B13-01869-02, Internal Core Spray Line Flaw Evaluation for Pilgrim Nuclear Power Station ML20128G5361996-09-30030 September 1996 Safe Shutdown Equipment List Rept for Resolution of USI A-46 ML20128G5871996-09-30030 September 1996 Relay Evaluation Rept for Resolution of USI A-46 ML20128G5621996-09-30030 September 1996 Seismic Evaluation Rept for Resolution of USI A-46 ML20133N5631996-03-25025 March 1996 SE for Pilgrim Nuclear Power Station ML20133N5781996-03-25025 March 1996 SE for Pilgrim Nuclear Power Station ML20133N6401996-01-31031 January 1996 Effects of Fiberglass Insulation Debris on Pilgrim ECCS Pump Performance, to GE-NE-B13-01805-11 ML20084J5081995-03-31031 March 1995 Rev 2 to GE Responses to NRC Questions for Pilgrim Shroud Repair ML20081D0911995-03-0909 March 1995 Training Simulator Submittal for NRC Certification 1995 ML20205D4471995-01-0101 January 1995 Boston Edison Co Master Decommissioning Trust Agreement for Pilgrim Nuclear Power Station ML20077Q1251994-11-0101 November 1994 Boston Edison Requirements for Seismic Analysis for General Electric RPV Shroud Repair Project ML20079S2361994-10-13013 October 1994 Reduction in IGSCC Insp Frequencies ML20073A2201994-09-0909 September 1994 Executive Summary from Technical Rept 93177-TR-03,Rev 0 Re Plant Reactor Vessel Cumulative Usage Factor ML20134B0311993-10-31031 October 1993 Final Rept Evaluation of Effects of Using Various Damping Values in Seismic Analysis of PNPS Piping Sys ML20064K8341993-07-31031 July 1993 Seismic Reanalysis of Reactor Bldg Pilgrim Nuclear Power Station ML20056E2341993-07-31031 July 1993 Preservice Exam of Reactor Water Cleanup Sys Piping,Ninth Refueling & Insp Outage Rept of Exam Results by Ge ML20065L7851993-07-30030 July 1993 Seismic Reanalysis of Reactor Building Pilgrim Nuclear Power Station ML20128P3731993-01-0505 January 1993 Spent Fuel Storage Capacity Expansion ML20117K8951992-07-0909 July 1992 IPEEE Plymouth,Ma ML20059M1581992-04-0303 April 1992 Rev 0 to Engineering Evaluation ML20065L5961990-11-30030 November 1990 Dcrdr, Final Summary Rept ML20058E3771990-10-31031 October 1990 Investigation of Leukemia Incidence in 22 Ma Communities 1978-1986 ML20011D1651989-12-31031 December 1989 Final Assessment Rept. ML20246M3531989-06-30030 June 1989 Augmented Offgas Control Panel CP-600 Surface Enhancements ML20246K1891989-04-30030 April 1989 Dcrdr Supplementary Summary Rept ML20155B9601988-10-0505 October 1988 Bg&E Rept on Status of Offsite Emergency Preparedness Around Pilgrim Nuclear Power Station ML20154G2031988-09-30030 September 1988 Response to NRC Bulletin 88-05 & Suppls 1 & 2,Nonconforming Matls ML20204J4011988-09-14014 September 1988 Reg Guide 1.97 Compliance Evaluation for Pilgrim Nuclear Power Station I ML20235R4361988-07-0707 July 1988 Independent Review of Adequacy of Power Ascension Program Testing ML20150C0201988-05-26026 May 1988 Self Assessment of Readiness for Restart ML20206B9151988-05-12012 May 1988 Feasibility of Exposure Assessment for Pilgrim Nuclear Power Plant, Final Project Rept ML20077E5481988-01-31031 January 1988 Evaluation of RTV Coatings for Post Insulators, Interim Rept ML20117K9051987-12-31031 December 1987 Tornado Hazard to Class 1 Electrical Conduits at Pilgrim Nuclear Generating Station ML20154E1601987-12-16016 December 1987 Rept on Emergency Preparedness for Incident at Pilgrim Nuclear Power Station ML20065A8711987-11-30030 November 1987 Nuclear Lemon,Ratepayer Savings from Retiring Pilgrim Npp ML20207A6861987-09-11011 September 1987 Leukemia Incidence in Communities in Vicinity of Pilgrim I Nuclear Power Generating Station. Related Info Encl ML20150D1191987-08-31031 August 1987 Drywell Temp Analysis ML20235A5381987-07-31031 July 1987 Rept of Special Committee Established for Purpose of Making Investigation & Study Re Pilgrim Nuclear Generating Facility as Plymouth Under Provisions of Senate Order 2044 Adopted in 1986 ML20245C2791987-07-31031 July 1987 Rept of Special Committee Established for Purpose of Making Investigation & Study Re Pilgrim Nuclear Generating Facility ML20245C2321987-07-29029 July 1987 FEMA Comments on Rept to Governor on Emergency Preparedness for Accident at Pilgrim Nuclear Power Station ML20235P2831987-07-0101 July 1987 Rept on Pilgrim Station Safety Enhancements ML20236C3961987-05-15015 May 1987 Marked-up Rev 0 to Safety Evaluation Re Proposed Direct Torus Vent to Main Stack ML20213F2631987-04-30030 April 1987 Boston Edison Co Response to Generic Ltr 84-11: 'Insp of BWR Stainless Steel Piping,' Summary Overview ML20234A7521987-03-31031 March 1987 Rept to Selectmen on Plymouth Radiological Emergency Response Plan ML20237A0481987-01-31031 January 1987 Evaluation of Offsite Emergency Preparedness in Area Surrounding Pilgrim Nuclear Power Station ML20205S5211987-01-23023 January 1987 RHR Pump Wear Ring Surveillance Exam Results, Final Rept ML20237A0391986-12-16016 December 1986 Rept to Governor on Emergency Preparedness for Accident at Pilgrim Nuclear Power Station 1999-03-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3021999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pilgrim Nuclear Station.With ML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20216F3511999-09-0808 September 1999 ISI Summary Rept for Refuel Outage 12 at Pnps ML20216E6881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pilgrim Nuclear Power Station.With ML20210R3401999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Pilgrim Nuclear Power Station.With ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co 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 ML20209E6191999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Pilgrim Nuclear Power Station.With ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209B9861999-06-23023 June 1999 Rev 13A to Pilgrim Nuclear Power Station COLR for Cycle 13 ML20217N9061999-06-21021 June 1999 Rept of Changes,Tests & Experiments for Period of 970422-990621 ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20195G8231999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Pnps.With ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20206J6611999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Pilgrim Nuclear Power Station.With ML20205L0221999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Pilgrim Nuclear Power Station.With ML20207J5471999-03-0909 March 1999 Training Simulator,1999 4-Yr Certification Rept ML20207F9401999-03-0101 March 1999 Long Term Program Semi-Annual Rept for Pilgrim Nuclear Power Station ML20207H5451999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Pilgrim Nuclear Power Station.With ML20196E2151998-12-31031 December 1998 1998 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept.With ML20206Q2741998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Pilgrim Nuclear Power Station.With ML20197J3591998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Pilgrim Nuclear Power Station.With ML20195C9951998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Pilgrim Nuclear Power Station.With ML20154K0721998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Pilgrim Nuclear Power Station.With ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20197C5011998-09-0404 September 1998 Rev 12C,Pages 4 & 5 to Pilgrim Nuclear Power Station Colr ML20197C5471998-08-31031 August 1998 Rev 12C to Pilgrim Nuclear Power Station Colr ML20151W8231998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Pilgrim Nuclear Power Station.With ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20237A9941998-07-31031 July 1998 Monthly Operating Rept for Pilgrim Nuclear Power Station ML20236U8201998-07-13013 July 1998 Rev 12B to Pilgrim Nuclear Power Station COLR (Cycle 12) ML20236P0151998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Pilgrim Nuclear Power Station ML20249A3741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Pilgrim Nuclear Power Station.W/Undated Ltr ML20247H2081998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Pilgrim Nuclear Power Station ML20207B7601998-03-31031 March 1998 Final Rept, Pilgrim Nuclear Power Station Site-Specific Offsite Radiological Emergency Preparedenss Prompt Alert & Notification System Quality Assurance Verification, Prepared for FEMA ML20216G3911998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Pilgrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20248L2241998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Pilgrim Nuclear Station ML20202G5251998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Pilgrim Nuclear Power Station ML20236M8511997-12-31031 December 1997 1997 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept ML20198L7701997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station ML20203D6101997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Pilgrim Nuclear Power Station ML20202D5761997-11-0808 November 1997 1997 Evaluated Exercise BECO-LTR-97-111, Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20217H5621997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Pilgrim Nuclear Power Station ML20216J4131997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Pilgrim Nuclear Power Station ML20210J3321997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Pilgrim Nuclear Power Station 1999-09-08
[Table view] |
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Safety Evaluation NED Proposed Change No.: [')$ Reo l SAFETY EVALUATION PILGRIM NUCLEAR POWER STATION Rev. No.
F"C . C# System Calc.
Group: No.: Name: No.: Date:
Initiator: Dept:
ge.o ~PEMS. Tl4 8&20 ARR M 269 6/Gl#6 M &a,.4 %.o Description of Proposed change, test or experiment:
EsLAhskm J rd a T e nm,-m r naoJiL ra h ca L.a A.1 l sea L h M ft si sAew - ne.,
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SAFETY EVALUATION CONCLUSIONS:
The proposed change, test or experiment:
- 1. (4 Does Not ( ) Does increase the probability of occurrence or consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR.
- 2. ( W Does Not ( ) Does increase the possibility for accident or malfunction of a different type than any evaluated previously in the FSAR.
- 3. ( 4 Does Not ( ) Does decrease the margin of safety as defined in the basis for any technical specification.
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Safety Evaluaticn No.: J4t* 1c)$7 Rea l SAFETY EVALUATION PILGRIM NUCLEAR POWER STATION Rev. No. Z A. APPROVAL (14) (v7 This proposed change does not involve a change in the Technical Specifications Ref.10CFR50.59(c).
(14) (v1 Thisproposedchange,testorexperimentdoes()doesnot(g involve an unreviewed safety question as defined in 10CFR, Part 50.59(a)(2).
(15) (-r" This proposed change involves a change to the FSAR per 10CFR 50.71(e) and is reportable under 10CFR50.59(b).
(15) ( ) Comments:
(16) The safety evaluation basis and conclusion is:
( [ Approved () Not Approved F N a - Tela dzr/g (17)
Discipline Group Leader /D' ate Supporting Discipline Group Leader /Date B. REVIEW APPROVAL (18) ( ) Comments:
(19) U S8$A Group Leader /Date' N hl @
O C. ONC NEVIEW
! (20) ( ) This proposed change involves an unreviewed safety question and a requests for authorization of this change must be filed with j
the Directorate of Licensing, NRC prior to implementation.
1 (20)"( d This proposed change does not involve an unreviewed safety question.
, (21) ORC Chairman b Date (,//C,/FC (21)
() U l (22) ORC Meeting Number F4 - Po
! cc:
! Exhibit 3.07-A Rev. 2 Sheet 2 of 3 A6-3 i
PILGRIM STATION FSAR REVIEW SHEET
References:
Date: I} N Safety Evaluation: Ik N Rev. No.: l Support a change List FSAR test, diagrams, and indices affected by this change and corresponding FSAR revision.
Affected FSAR Revision to affected FSAR Section isFinal shown on:
Preliminary Section O f/(y b Attachment 1 P1O Wktd W II Attachment 2 L. as Y Attachment 3 vvv.
Attachment 4 Attachment 5 Attachment 6 PRELIMINARY FSAR REVISION (to be completed at time of Safety Evaluation preparation).
niit tousu.
Prepared by ,W /Uate: InII ? o 6v Kev 1eweo oy:
O i i /
l Approved by: 2 /Date:
I FINAL FSAR REVISION (Prepared following operational turnover of related systems structures of components for use at PNPS). (1)
/Date: Reviewed by: /Date:
Prepartd by:
l l
Attach completed FSAR Change Request Form (Refer to NOP).
(1)
Exhibit 3.07-A Rev. 2.
Sheet 3 of 3 A6-4
E Safety Evaltation No.: 19 5
- SAFETY EVALUATION WORK SHEET Rev. No. /
A. System Structure Component Failure and Consequence Analyses.
System Structure Component Failure Modes Effects of Failure Comnents 1.
bd ~
2.
3.
General Reference Material Review REGULATORY CALCULATIONS FSAR SECTION PNPS TECHNICAL SPECS.
DESIGN SPECS PROCEDURES GUIDES STANDARDS CODE a.s A T S . 3.5. A M- 2 69 Res . 0 loc M So k I 3N0 $.7. l. 3 l 8.9. l.f ASINF8+ PV W I
B. For the proposed hardware change, identify the failure modes For thateachare likely for the components consistent with FSAR assumpti components. Especially show how the failure (s) affects the assigned safety basis (FSAR Text for each system) or plant safety functions FSAR Chapter 14 and Appendix G).
b -
Date_'l'5fd6 i Prepared by ~U U NOTE:
It is a requirement to include this work sheet with the Safety Evaluation.
Rev. 2 Exhibit 3.07-C A6-5 l
J SE bo.8 59 %, l.
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d* WOMENT THE EST ABLt THNSF 4EAKAgE (AsAvaR A LEAK Age pt. ATE OF 0F A c o uvao,.ts b tw Ao TH'AT At.Locue, I l O @M W'R A ' 'OW WGR t] MbR I1 le t Fit. m STABtLleAto4 oF R4P-THc oE4RebArron 39SM ? RET S ORE ,'fET ep %,yg,g APPENb:x ,7 (I E-) LEAK A4r pAsT No%.* w I.o GPM WW N OPENA ro. o,. , m ,) m'ew. is tus rw Ta se aa-a T*H e e ewivAccur
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ATTACHMENT 7 Plan and Schedule Details Regarding Long Term Actions i
l l
l
Additional Details ,
Item C (Spurious Isolation) Reference (C), Page 1 According to the most current Long Term Program, the EPIC computer project implementation is scheduled for completion 3/31/87. That completion date is based on a September 1986 refueling outage. Approximately four months after return to power from the outage are required to complete system acceptance tests allowing for contingency.
Refueling Outage 7 is being rescheduled to commence in January, 1987. However, a firm start date and duration have not yet been established. EPIC completion will be scheduled (4) months after return to power from RFO #7.
Item C.6 Trend Surveillance History of 400 psig Valve interlock for reliability. Reference (B), Attachment (4), Page 6 of 6 The results of Surveillance Test 8.M.2-2.1.8 of Pressure Switches 263-52A and 52B for the RHR injection valve opening permissive have been compiled for the five year period ending in April, 1986. The switch has always actuated at a 100% rate. The incidence where recalibration was needed to restore the setpoint to within Technical Specification limit is 3 occurrences out of 40 (20 tests per switch) or a 92.7% calibr-tion reliability rate. The present calibration frequency is sufficient to assure proper setpoint; therefore, an increase in test frequency is not warranted.
The recommendation of the RHR Task Force Item C.6 has, therefore, been completed by this compilation and analysis.
Special Training Plan for Union and Management Operations Personnel Prior to Station Startup l
l Prior to the Union Operations Personnel resuming watch standing duties they will receive training as outlined in the following i schedule.
In addition, all Management Operations Personnel, including STA's, will receive the following training prior to station startup..
A7-1 l
r:1 1 I
SPECIAL REQUALIFICATION TRAINING SESSION 11A SCHEDULE TIME:
8:00AM - 8:30AM Revised Training Schedule H. Balfour T. Sullivan 8:30AM - 9:00AM Management Changes / Current P. Mastrangelo Plant Status 9:00AM - 12:00PM Plant Modification Update t
3
- Complete review of "BEC0 R. Woodard.
! Response to NRC Cal 86-10" G. Sherman (includina all related Temocrary Procedures)
MSIV i RHR j Mode Switch
- Temporary Modifications D. Hughes 86-14, Change feedwater
, heater 105B outlet valve, M03480, from seal-in to jog 2
- 86-19, Diesel Generator "A" 1 Relaying Modification l 12:00AM-12:30PM Lunch
- 12:30PM - 4:30PM Significant Industry Events J. Klein
- - SER 37 Premature Critical-ity Due to Control Rods Being Improperly Withdrawn SER 13 Control Rod Mis- J. Klein l operation i
j- -
SER 18 Diesel Generator D. Hughes Differential Relays Non Seismically Qualified a
l l
1 i
i f A7-2
( __ _
r Miscellaneous Events J. Klein R. Woodard
- Technical Specifications G. Sherman Amendment #94
- Current Memos Procedure Review
- 1.3.34 Conduct of Operations 2.1.1 Startup from Shutdown
- 2.1.16 N.P.O. Tour
- 2.2.22 R.C.I.C.
- 2.2.84 Reactor Recirculation System 2.3.2.1 Panel 903 Left
- 2.4.21 Double ended break of 3" instrument air / nitrogen line in drywell
- 2.4.31 Reactor basin / spent fuel pool drain down i
l A7-3
.