Letter Sequence Meeting |
|---|
TAC:44876, (Approved, Closed) TAC:45699, (Approved, Closed) TAC:51119, (Open) TAC:52032, (Open) TAC:52867, (Approved, Closed) TAC:53415, (Approved, Closed) TAC:53702, (Approved, Closed) TAC:54610, (Approved, Closed) TAC:59127, (Open) TAC:59190, (Approved, Closed) TAC:60465, (Approved, Closed) TAC:61370, (Approved, Closed) TAC:61634, (Open) TAC:62850, (Approved, Closed) TAC:64377, (Approved, Closed) |
|
MONTHYEARML20138B5931985-10-31031 October 1985
Conformance to Reg Guide 1.97,Pilgrim Nuclear Power Station
Project stage: Other
ML20245A4481986-09-30030 September 1986
Revised Draft Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1
Project stage: Draft Other
ML20244E3751986-10-10010 October 1986
Forwards SER & SALP Input Accepting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Identifying, Classifying & Treating Components Required for Performance of Reactor Trip Function as safety-related
Project stage: Approval
IA-87-644, Forwards SER & SALP Input Accepting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Identifying, Classifying & Treating Components Required for Performance of Reactor Trip Function as safety-related1986-10-10010 October 1986
Forwards SER & SALP Input Accepting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Identifying, Classifying & Treating Components Required for Performance of Reactor Trip Function as safety-related
Project stage: Approval
BECO-87-016, Advises That Timer & Keylocked Manual Inhibit Switches Will Be Installed,Per Util 860924 Commitment to Modify Automatic Depressurization Sys to Address Concerns Re NUREG-0737,Item II.K.3.181987-01-28028 January 1987
Advises That Timer & Keylocked Manual Inhibit Switches Will Be Installed,Per Util 860924 Commitment to Modify Automatic Depressurization Sys to Address Concerns Re NUREG-0737,Item II.K.3.18
Project stage: Other
ML20212M5271987-03-0303 March 1987
Amend 99 to License DPR-35,revising Tech Spec Requirements for Certain Instrument Channel Test & Calibr Frequencies to Once Per Operating Cycle During Refueling Outages
Project stage: Other
ML20206G8031987-03-26026 March 1987
Forwards Safety Evaluation Granting Inservice Insp Program Relief Requests PRR-8 Re Surface & Volumetric Exam of RHR Sys HX Nozzles & PRR-9 Re Exam of 100% of Required Vol for nozzle-to-vessel Welds,Per Util 860415 & 1212 Ltrs
Project stage: Approval
ML20214Q4191987-06-0101 June 1987
Forwards Summary of Nrr/Util 870521 Meeting Re Licensing Issues for Plant.List of Attendees Also Encl
Project stage: Meeting
ML20236D1441987-07-22022 July 1987
Forwards Branch SER & SALP Input Re Util Request to Modify Standby Liquid Control Sys Tech Specs for Consistency W/Atws Rule (10CFR50.62.C.4).Request Acceptable
Project stage: Other
ML20207A5801987-08-0505 August 1987
Forwards SER & SALP Input Re Util 870401 Request for Exemption from 10CFR50,App R,Section Iii.J Requirement to Install 8 H Battery Powered Lighting in Outside Yard Area. Exemption Should Be Granted
Project stage: Approval
BECO-87-158, Responds to 870714 Request for Addl Info Re Second 10-yr Interval Inservice Insp Program Plan.Ref List of Calibr Blocks,Including Identifications,Matl Specs & Sizes Encl1987-10-0202 October 1987
Responds to 870714 Request for Addl Info Re Second 10-yr Interval Inservice Insp Program Plan.Ref List of Calibr Blocks,Including Identifications,Matl Specs & Sizes Encl
Project stage: Request
BECO-87-173, Updates Info Provided in Re Inservice Insp Exams. NRC Should Note That Insp Discussed on 861212,when Performed,Will Complete First Insp Period of Second Ten Yr Inservice Insp Interval.Supporting Info Encl1987-11-0505 November 1987
Updates Info Provided in Re Inservice Insp Exams. NRC Should Note That Insp Discussed on 861212,when Performed,Will Complete First Insp Period of Second Ten Yr Inservice Insp Interval.Supporting Info Encl
Project stage: Other
ML20236T1101987-11-25025 November 1987
Notification of 871210 Meeting W/Util in Bethesda,Md to Discuss Ongoing Inservice Pump & Valve Test Program Review. Proposed Agenda Encl
Project stage: Meeting
ML20236X0971987-11-25025 November 1987
Cancelled Notification of 871210 Meeting W/Util in Bethesda, MD to Discuss Ongoing Inservice Pump & Valve Test Program Review.Meeting to Be Rescheduled in Jan
Project stage: Meeting
BECO-87-195, Submits Current Status of Improvements Being Implemented in Response to NUREG-0737,Item II.F.2 & Generic Ltr 84-23. Improvements Include Instrumentation for Reactor Water Level Sys & Installation of Analog Trip Sys1987-12-0808 December 1987
Submits Current Status of Improvements Being Implemented in Response to NUREG-0737,Item II.F.2 & Generic Ltr 84-23. Improvements Include Instrumentation for Reactor Water Level Sys & Installation of Analog Trip Sys
Project stage: Other
ML20237B1351987-12-10010 December 1987
Summary of 871124 Meeting W/Util & Member of Public Re Fire Protection Issues at Plant.Meeting Agenda,List of Attendees & Summary of Significant Matters Discussed Encl
Project stage: Meeting
BECO-87-207, Provides Addl Info Re Second 10-yr Interval Inservice Insp Program Plan,Per Util 871002 Commitment & NRC 870714 Request.Attachment 2 Is Overall Revised Component Listing, Including 26 Addl Welds1987-12-28028 December 1987
Provides Addl Info Re Second 10-yr Interval Inservice Insp Program Plan,Per Util 871002 Commitment & NRC 870714 Request.Attachment 2 Is Overall Revised Component Listing, Including 26 Addl Welds
Project stage: Other
ML20205F0051988-02-0505 February 1988
Discusses Resolution of Fire Protection Licensing Actions
Project stage: Other
BECO-88-026, Forwards GE Proprietary Rept, Tech Spec Improvement Analysis for Reactor Protection Sys for Pilgrim Nuclear Power Station, Supporting Proposed Changes to Tech Spec Tables 3.1.1 & 3.2.A.Rept Withheld (Ref 10CFR2.790(b)(1))1988-02-22022 February 1988
Forwards GE Proprietary Rept, Tech Spec Improvement Analysis for Reactor Protection Sys for Pilgrim Nuclear Power Station, Supporting Proposed Changes to Tech Spec Tables 3.1.1 & 3.2.A.Rept Withheld (Ref 10CFR2.790(b)(1))
Project stage: Request
ML20150C7401988-03-0808 March 1988
Provides Info Re Status of Inservice Insp & Augmented IGSCC Insp Programs for Plant 1987 Refueling Outage
Project stage: Other
ML20150C7641988-03-0808 March 1988
Advises That 860922 & 870506 Details of Inservice Insp & Augmented IGSCC Insp Program for 1987 Refueling Outage Meets Guidelines of Generic Ltr 84-11 & Acceptable
Project stage: Other
BECO-88-048, Forwards Rev 1B to Inservice Testing Program for Pumps & Valves,Second Ten Yr Interval,Pilgrim Nuclear Power Station1988-03-14014 March 1988
Forwards Rev 1B to Inservice Testing Program for Pumps & Valves,Second Ten Yr Interval,Pilgrim Nuclear Power Station
Project stage: Other
BECO-88-047, Forwards Responses to NRC Concerns Re Rev 1A of Inservice Testing (IST) Program for Pumps & Valves for Plant.Util Plan for Upgrading Current IST Program Establishes More Viable Pump & Valve Testing Program W/O Major Impact on NRC Review1988-03-14014 March 1988
Forwards Responses to NRC Concerns Re Rev 1A of Inservice Testing (IST) Program for Pumps & Valves for Plant.Util Plan for Upgrading Current IST Program Establishes More Viable Pump & Valve Testing Program W/O Major Impact on NRC Review
Project stage: Other
ML20207A9631988-04-20020 April 1988
Forwards Request for Addl Info Re Util 831107 & 840427 Responses to Generic Ltr 83-28,Item 2.2 (Part 2), Vendor Interface (Programs for All Other Safety-Related Components)
Project stage: RAI
ML20153E0601988-05-0404 May 1988
Forwards Request for Addl Info Re Generic Ltr 83-28,Item 2.2 (Part 2), Vendor Interface (Programs for All Other Safety- Related Components), Needed in Order for NRC to Complete Review
Project stage: RAI
ML20207B0121988-06-0303 June 1988
Forwards SER Re Util Request for Exemption from Specific Technical Requirements of Section Iii.G of App R to 10CFR50. Exemption Should Be Granted.Salp Input Also Encl
Project stage: Approval
ML20151D0461988-07-18018 July 1988
Forwards Safety Evaluation Supporting Response to Generic Ltr 83-28,Item 2.2.1, Vendor Interface (Programs for All Other Safety-Related Components)
Project stage: Approval
ML19318G8961988-09-28028 September 1988
Forwards SER & Topical Rept EGG-MS-8042, Technical Evaluation Rept on Second 10-Yr Interval Inservice Insp Program Plan, Accepting Util Program,Per 10CFR50.55a(g)(4)
Project stage: Approval
BECO-89-042, Responds to 890117 Request for Addl Info Re NUREG-0737,Item II.E.4.2(7), Automatic Isolation of Containment Purge & Vent Valves. Given Multiple & Diverse Alarms of Reactor Coolant Leakage,Adequate Detection of Leak Assured1989-03-27027 March 1989
Responds to 890117 Request for Addl Info Re NUREG-0737,Item II.E.4.2(7), Automatic Isolation of Containment Purge & Vent Valves. Given Multiple & Diverse Alarms of Reactor Coolant Leakage,Adequate Detection of Leak Assured
Project stage: Request
ML20244D2841989-04-11011 April 1989
Responds to Request for Addl Info Re Rev 3 to Reg Guide 1.97, Emergency Response Capability. Instrumentation Used to Monitor Status of Standby Power Sys & Energy Sources Important to Safety Listed
Project stage: Request
ML20247P5501989-06-0101 June 1989
Forwards Request for Addl Info on Proposed Tech Specs Change Re Visual Insp of High Energy Piping.Listed Concerns Based on Review of Bechtel Calculation 17322-S5,Rev 1
Project stage: RAI
BECO-89-090, Responds to NRC Verbal Request for Addl Info Re NUREG-0737, Item II.E.4.2(7) Requirement for Automatic Isolation of Containment Purge & Vent Valves.Submittal Provides Summary of Changes Made to Alarm Response Procedures1989-06-30030 June 1989
Responds to NRC Verbal Request for Addl Info Re NUREG-0737, Item II.E.4.2(7) Requirement for Automatic Isolation of Containment Purge & Vent Valves.Submittal Provides Summary of Changes Made to Alarm Response Procedures
Project stage: Request
BECO-89-124, Responds to Request for Addl Info Re Proposed Tech Spec Change on Visual Insp of High Energy Piping Outside Primary Containment During Plant Operation.Bechtel Calculation Re Pipe Break Outside Containment Encl1989-08-21021 August 1989
Responds to Request for Addl Info Re Proposed Tech Spec Change on Visual Insp of High Energy Piping Outside Primary Containment During Plant Operation.Bechtel Calculation Re Pipe Break Outside Containment Encl
Project stage: Request
BECO-90-005, Provides Bases for Environ Qualification of Instrumentation Monitoring Effluent Radioactivity & Status of Standby Power Per Reg Guide 1.97,Rev 3 & Generic Ltr 82-331990-01-11011 January 1990
Provides Bases for Environ Qualification of Instrumentation Monitoring Effluent Radioactivity & Status of Standby Power Per Reg Guide 1.97,Rev 3 & Generic Ltr 82-33
Project stage: Other
BECO-90-010, Forwards Summary of Compliance W/Reg Guide 1.97,Rev 3 Re Emergency Response Capability.Util Endorses BWR Owners Group Position That Fully Qualified Class 1E post-accident Neutron Monitoring Sys Inappropriate1990-01-15015 January 1990
Forwards Summary of Compliance W/Reg Guide 1.97,Rev 3 Re Emergency Response Capability.Util Endorses BWR Owners Group Position That Fully Qualified Class 1E post-accident Neutron Monitoring Sys Inappropriate
Project stage: Other
ML20072P7751990-06-30030 June 1990
Conformance to Reg Guide 1.97:Pilgrim
Project stage: Other
BECO-91-040, Forwards Summary of Compliance W/Reg Guide 1.97,Rev 2 to Assist NRC in Review of Compliance W/Reg Guide 1.97,Rev 3, Per 9100115 & 0405 Ltrs1991-03-20020 March 1991
Forwards Summary of Compliance W/Reg Guide 1.97,Rev 2 to Assist NRC in Review of Compliance W/Reg Guide 1.97,Rev 3, Per 9100115 & 0405 Ltrs
Project stage: Other
BECO-91-066, Forwards Updated Summary of Compliance W/Reg Guide 1.97 & Responds to NRC SER1991-05-13013 May 1991
Forwards Updated Summary of Compliance W/Reg Guide 1.97 & Responds to NRC SER
Project stage: Other
1988-02-05
[Table View] |
Forwards Summary of Nrr/Util 870521 Meeting Re Licensing Issues for Plant.List of Attendees Also Encl| ML20214Q419 |
| Person / Time |
|---|
| Site: |
Pilgrim |
|---|
| Issue date: |
06/01/1987 |
|---|
| From: |
Wessman R
Office of Nuclear Reactor Regulation |
|---|
| To: |
Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| TASK-2.E.4.2, TASK-2.K.3.18, TASK-TM TAC-44876, TAC-45699, TAC-51119, TAC-52032, TAC-52867, TAC-53415, TAC-53702, TAC-54610, TAC-59127, TAC-59190, TAC-60465, TAC-61370, TAC-61634, TAC-62850, TAC-64377, NUDOCS 8706050020 |
| Download: ML20214Q419 (6) |
|
Text
_
UN O I I387 Docket No. 50 293 MEMORANDUM FOR:
File FROM:
R. H. Wessman, Senior Project Manager Project Directorate I-3 Division of Reactor Projects I/II, NRR
SUBJECT:
MEETING MINUTES - MEETING BETWEEN BOSTON EDIS0N COMPANY AND NRC ON MAY 21, 1987 On May 21, 1987, representatives of Boston Edison Company (BEco) met with members of NRR to discuss licensing issues regarding the Pilgrim Nuclear Power Station. Significant matters discussed are summarized on Enclosure 1 to this memorandum. Attendees are listed on Enclosure 2 to this memorandum.
I i
R. H. Wessman, Senior Project Manager Project Directorate I-3 Division of Reactor Projects I/II
Enclosures:
As stated cc: See attached DISTRIBUTION S. Varga B. Boger PDR/LPDR R. Wessman
- 0. Gormley J. Wiggins, RI 0FC :PDI-3
- P
-3
- PDI-
___...j.}.{_..___,________.__:____________:____________:___________
NAME :RWe, man
- MRush ok /.VNs sEs, t
DATE :9/Y)/87
- /
87
- 6/ / /87
/
OFFICIAL RECORD COPY 8706050020 870601 PDR ADOCK 05000293 F
PDR
~
Mr. Ralph G. Bird Boston Edison Company Pilgrim Nuclear Power Station cc:
Mr. K.
P.' Roberts, Station Manager Boston Edison Company M/C Nuclear Boston Edison Company ATTN: Ralph G. Bird RFD #1, Rocky Hill Road Senior Vice President - Nuclear Plymouth, Massachusetts 02360 800 Boylston Street Boston, Massachusetts 02199 Resident Inspector's Office U. S. Nuclear Regulatory Commission Post Office Box 867 l
Plymouth, Massachusetts 02360 Chairman, Board of Selectmen 11 Lincoln Street Plymouth, Massachusetts 02360 Office of the Commissioner Massachusetts Departrent of Environmental Quality Engineering One Winter Street Boston, Massachusetts 02108 Office of the Attorney General l
1 Ashburton Place 19th Floor Boston, Massachusetts 02108 Mr. Robert M. Hallisey, Director Radiation Control Program Massachusetts Department of Public Health 150 Tremont Street, 2nd Floor Boston, Massachusetts 02111 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. James D. Keyes Boston Edison Company 25 Braintree Hill Office Park Braintree,flassachusetts 02184
Matters Discussed Between Boston Edison Company and NRR Staff - May 21, 1987 NRC Licensina Items List 1.
(TAC 44876 - TMI Item II.E.4.2)
- BECo will provide information to the staff that follows owner's group program.
2.
(TAC 45699 - ADS Timer Logic) - The proposed supplemental information was discussed between staff and BECo.
Additional technical details are to be provided by BECo in early June.
3.
(TAC 52032 - 2nd Ten Year IST) - BECo technical material will be reexamined by NRR reviewer to assure questions of previous telephone conference call are addressed.
4.
(TAC 52867 - Salem ATWS Item 2.1) - BECo needs to provide additional detail to staff.
Information needs are similar to information requested in September 9, 1986 RAI to BECo on Salem ATWS Item 2.2 (TAC 53702).
5.
(TAC 59127 - 10CFR50.62 Rule) - Two of the three actions required by this rule are already implemented.
BECo has drafted prcposed Tech. Spec. regarding changes to the SBLC.
Staff agreed to determine if a request for an exemption to the rule will be necessary in the case of the Pilgrim SBLC system.
6.
(TAC 59190 - Appendix "J"
Isolation Valves) - BECo provided proposed supplement to thia proposed Tech. Spec., including.the revised Tech. Spec. pages.
Technical bases of previous submittals
~
are still applicable.
7.
(TAC 61634 - High Energy Piping) - Additional information is needed to supplement Bechtel technical information already irovided.
8.
(TAC 62850 - Hydrogen Water Chemistry) - This TAC also includes a Tech. Spec. change for main steam line radiation mon $ tors.
NRR reviewer (F. Witt) stated that staff SER on EPRI Guidelines would be completed in near future.
BECo submittal will describe electrolytic generation facility and hydrogen storage tank system, and provide system status plans for restart.
BECo plans to meet with the staff in mid-June to discuss the plant program.
s 9.
(TAC 51119 - Reg. Guide 1.97 Modifications) - BECo will supplement their letter of February 10, 1987 with additional information.
10.
(TAC 60465 - Tables 3.1.1 & 3.2.A) - NRR reviewer has been reassigned and PM needs to assure timely review.
11.
(TAC 64377 - Second 10-year ISI) - Completion of this review is expected by September 1987.
BECo to advise staff if higher priority is needed on this review.
12.
(TAC 61370 - Relief Requests for 10-year ISI) - Only part of this review has been completed (PRR 8 and 9).
Staff needs to complete the rest of this review.
Completion target is Sept-- er 1987, unless BECo advises staff of different priority.
13.
(TAC 54610 - Fire Protection Items) - The NRR reviewer (D.
Notley) met with BECo and PDI-3 to discuss this area.
BECo has developed an update to this submittal, including revised Tech.
Spec. pages.
However, portions of the technical supporting information from previous submittals still are applicable.
EECo agreed to schedule a meeting with the staff in the near future to help the staff understand all their desired changes.
A significant issue involving Appendix A and Appendix R barriers was identified, in that Tech. Specs. and License Conditions require adherence to both requirements.
BECo must develop a submittal requesting relief frem those Appendix A barriers that they desire to have removed from the license conditions.
This issue needs to be resolved expeditiously because of its impact on the outage scope.
14.
(TAC 53415 - Appendix R Exemption Requests) - DECO agreed to supply additional calculations to demonstrate why a fire in torus room cable trays would not harm overhead structural members.
15.
(TAC 60217 - Scram Insertion Time Surveillance) - BECo agreed to r vise the Tech. Spec. submittal to include testing after j
prolonged outages.
16.
(TAC 55571 - SBGT & CRHEAF Gystem) - As previously discussed with the PM, BECo agreed to revise this Tech. Spec. submittal to specify heater operability surveillance requirements.
II.
Hich Priority Items BECo and the staff agreed to a tentative prioritication of the submittal and review effort.
High priority items have been given a priority "1".
Items scheduled to be completed for plant restart are listed below:
e TAC 44876 - TMI II.E.4.2 Containment Isolation Dependability TAC 45699 - TMI II.K.3.18 ADS Actuation TAC 64610 - Fire Protection Issues TAC 59127 - 10CFR50.62 Reviews TAC 59190 - Appendix "J" Containment Isolation Valves TAC 62850 - Hydrogen Water Chemistry TAC 53416 - Appendix R Exemption Requests III.
Expected Submittals BECo and the staff discussed six submittals which are expected to be docketed in the near future.
All involve Tech. Spec. changes and all are expected to be completed by the staff in time to support facility restart.
These submittals will involve the following subjects:
HPCI and RCIC Operability Tech. Spec.
APRM Downscale Scram Tech. Spec.
Reload 7 Licensing Submittal and Tech. Spec.
Undervoltage Relays in Table 3.2.B Tech. Spec.
ATWS RPT/ARI Instrumentation Tech. Spec.
Control Rod Block Actuation Tech. Spec.
1
4 e
List of Attendees R
Fairbank Boston Edison Co.
J.
Keyes Boston Edison co.
R. Wessman NRR O.
Gormley NRR F. Witt (part time)
NRR D. Notley (part time)
NRR B. Boger (part time)
NRR S.
Varga (part time)
NRR
.