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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20211A4361999-08-18018 August 1999 Notification of Significant Licensee Meeting 99-47 with Entergy Nuclear,Inc on 990831 to Discuss Results of NRC Plant Performance Review of Pilgrim Nuclear Power Station Issued on 990409 ML20212H7621999-06-22022 June 1999 Notification of 990701 Meeting with NEI & Entergy in Rockville,Md to Discuss Price-Anderson Issues Re Transfer of Pilgrim License from Beco to Entergy ML20205L0301999-04-0909 April 1999 Notification of 990413 Meeting with Boston Edison Co & Entergy Nuclear Generation Co in Rockville,Md to Discuss Sale & Transfer of Pilgrim Station from Boston Edison Co to Entergy Nuclear Generation Co ML20196J5801998-12-0707 December 1998 Notification of 981209 Meeting with Representatives of Beco & Entergy in Rockville,Md to Discuss Sale of Pilgrim Plant ML20196F3461998-12-0202 December 1998 Forwards Info Re Operator Licensing Exam Administered on 981016-23 at Pilgrim Station,For Distribution Under Rids Code IE42 ML20196F5611998-12-0202 December 1998 Forwards Info Re OL Exam Administered on 981016-23 at Pilgrim Station,For Distribution Under Rids A070 ML20154D5091998-10-0202 October 1998 Notification of Meeting W/Beco on 981008 in Rockville,Md to Discuss Core Spray Piping Integrity ML20154G5141998-10-0202 October 1998 Notification of 981008 Meeting W/Beco in Rockville,Md to Discuss Core Spray Piping Integrity.Meeting Has Been Rescheduled to 981015 ML20247G2441998-04-15015 April 1998 Notification of Significant Licensee Meeting 98-34 W/Util on 980427 to Discuss Weaknesses in Licensee Alarm Assessment Program (EA 98-191) ML20203E2781998-02-19019 February 1998 Notification of Significant Licensee Meeting 98-18 W/Util in King of Prussia,Pa on 980310 Re Plant Design Basis Project Discussion ML20199C7581997-10-31031 October 1997 Notification of Significant Licensee Meeting 97-112 W/Util on 971113 to Discuss NRC SALP ML20212D6201997-10-28028 October 1997 Notification of Licensee Meeting on 971121 W/Util in King of Prussia,Pa to Discuss Apparent Violations Identified During NRC Insp 50-293/97-05 ML20140F6151997-06-11011 June 1997 Notification of 970612 Meeting W/Util in Rockville,Md to Discuss Net Positive Suction Head for ECCS Pumps ML20137Q9761997-03-31031 March 1997 Informs That as-found LOCA & Life Testing & Analysis Does Not Provide Acceptable Approach for Demonstrating Qualification at Accident Temp Higher than 340F,per 970110 TAR ML20137B4781997-03-14014 March 1997 Undated Memo Discussing Beco Reorganization ML20141A7361997-03-12012 March 1997 Rcommends That Key RES Staff Attend Subcommittee Meetings to Address Any Questions,Arise in Discussions Among Members & to Answer Any Key Questions Posed in Advance by Subcommittee Chairmen ML20149M3291996-11-12012 November 1996 Forwards Input Re TIA on Plant Licensing Basis & Subsequent Mod Under 10CFR50.59 for Two Safety Significant Problems ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20129D8331996-09-19019 September 1996 Notification of 961003 Predecisional Enforcement Conference 96-98 W/Util to Discuss Containment Penetration Protection. Meeting Closed to Public ML20134J7301996-07-26026 July 1996 Forwards Resolution of Spent Fuel Storage Pool Action Plan Issues Re Response to Two Postulated Event Sequences Involving SFP NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl IR 05000293/19930291993-11-23023 November 1993 Notification of Significant Licensee Meeting 93-156 W/Util on 931202 Re Three Recently Reported Design Issues in Insp Rept 50-293/93-29 ML20058C9711993-11-22022 November 1993 Notification of Significant Licensee Meeting 93-150 W/Util on 931217 Re Hpci/Rcic Reliability & Switchyard Betterment Status ML20059L9721993-11-12012 November 1993 Licensing Board Memorandum & Order Terminating Proceeding .* Informs That Time Provided by NRC Regulation to Review Decision of ASLB Terminating Proceeding in Docket Has Expired.W/Certificate of Svc.Served on 931112 ML20056C4721993-06-17017 June 1993 Discusses Util Assessment of Low Pressure Turbine Analysis. Licensee Retained Structural Integrity Assocs,Inc (SIA) to Evaluate Flaw Indications in 7GA Disk.Sia Anaylsis Reduce Some Obvious Conservatisms Used in GE Analysis ML20128F3911993-02-0303 February 1993 Requests Listed Instructions to Ensure That P Blanch of Northeast Utils & E Hadley of We the People Kept Promptly Informed of NRC Activities on BWR Water Level Indicators & Rosemount Transmitters ML20128E2181993-01-26026 January 1993 Notice of Significant Licensee Meeting 93-11 W/Licensee on 930225 in King of Prussia,Pa to Discuss Util Reorganization ML20059C1171992-11-20020 November 1992 Submits Status Rept on Reactor Water Level Spiking That Occurred on 921024.Related Info Encl ML20125D1161992-10-0707 October 1992 Notification of Significant Licensee Meeting 92-177 W/Util on 921217 to Discuss tie-in of New Security Computer ML20082B1581991-02-20020 February 1991 Summarizes Telcon W/R Murphy Re Mobilization Time for State of Ma Natl Guard Personnel Assigned to Respond to Wellesley, Ma Reception Ctr & State of Ma Civil Defense Agency Area II Headquarters in Event of Emergency at Facility ML20062H5361990-11-23023 November 1990 Forwards Info from Pilgrim Citizens Radiological Monitoring Network,Covering Rept Periods 900910-1017 ML20059P0861990-10-0101 October 1990 Notification of Significant Licensee Meeting 90-118 W/Util on 901016 to Discuss SALP ML20059L1541990-09-0707 September 1990 Notification of Significant Licensee Meeting 90-114 on 900912 at Region I Ofc to Discuss Corrective Actions & Restart Planning Re 900902 Manual Reactor Scram ML20059G4681990-08-0606 August 1990 Forwards Citizens Radiological Monitoring Network Weather Data Rept for Apr-Jul 1990 for Processing Through Nudocs Sys ML20127B4901990-08-0303 August 1990 Responds to 900726 Request for Recommendations for Appropriate Actions in Response to Inspector General Rept 90N-02 ML20127B4961990-08-0101 August 1990 Advises That Staff Did Not Conduct Thorough Review of Offsite Emergency Preparedness Which Resulted in Inaccurate Info Being Provided to Commission ML20058B4501990-06-28028 June 1990 Provides Status Rept Re Progress of off-site Emergency Preparedness Activities at Facility ML20055C2661990-02-0505 February 1990 Forwards Draft Ltr to Util Re Completion of Plant Power Ascension Program.Ltr Will Be Issued on 900209 Which Will Accept Util Completion of Power Ascension Program & Close Out Confirmatory Action Ltr CAL-86-10 ML20248C5841989-09-26026 September 1989 Notification of Significant Licensee Meeting 89-154 W/Util on 891006 in Plymouth,Ma to Discuss SALP Mgt ML20247N0121989-09-12012 September 1989 Forwards Plant Status Rept for 890826-0908.On 890830,reactor Automatically Scrammed Due to Fault on Main Generator Voltage Regulation Circuitry.On 890905,inadvertent Actuation LPCI Loop Select Logic Experienced ML20246N5751989-08-30030 August 1989 Forwards Plant Biweekly Status Rept for 890812-25 ML20245F6401989-08-0101 August 1989 Forwards Facility Biweekly Status Rept for 890715-28.NRC Restart Staff in Place & Onsite Monitoring Licensee Activities on Extended day-shift Basis During Reporting Period ML20247C0631989-07-19019 July 1989 Forwards Biweekly Status Rept for 890701-14.NRC Restart Staff in Place & Onsite & Monitoring Licensee Activities on around-the-clock Basis During Plant Startup & Power Ascension.Part 21 Related ML20247C1611989-07-14014 July 1989 Notification of Significant Licensee Meeting 89-112 W/Util on 890816 in King of Prussia,Pa to Discuss SALP ML20247E4531989-07-10010 July 1989 Forwards Plant Status Rept for 890617-30 Period.Rept Intended to Provide NRC Mgt & Public W/Overview of Plant Activities & NRC Restart Insp Activities ML20246K1141989-07-0303 July 1989 Notification of Significant Licensee Meeting 89-105/suppl Enforcement Conference Re Augmented Insp Team Findings Concerning 890412 Reactor Core Isolation Cooling Sys Overpressurization ML20245E6561989-06-22022 June 1989 Forwards Plant Biweekly Status Rept for 890603-16.On 890616, Reactor Operating at Approx 25% Power w/turbine-generator Synchronized to Grid.On 890612,util Commenced Controlled Reactor Shutdown to Perform Minor Mods,Maint & Testing ML20245F9581989-06-16016 June 1989 Notification of Significant Licensee Meeting 89-096 W/Util on 890619 in King of Prussia,Pa Re 890412 RCIC Sys ML20245A3311989-06-0909 June 1989 Notification of Significant Licensee Meeting 89-90 on 890627 W/Util in King of Prussia,Pa for Mgt Meeting to Discuss Status of Licensee Radiation Control Program ML20244E5081989-06-0707 June 1989 Forwards Biweekly Status Rept for 890520-0602.Rept Provides Overview of Plant Activities & NRC Restart Insp Activities. Part 21 Related 1999-08-18
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20211A4361999-08-18018 August 1999 Notification of Significant Licensee Meeting 99-47 with Entergy Nuclear,Inc on 990831 to Discuss Results of NRC Plant Performance Review of Pilgrim Nuclear Power Station Issued on 990409 ML20212H7621999-06-22022 June 1999 Notification of 990701 Meeting with NEI & Entergy in Rockville,Md to Discuss Price-Anderson Issues Re Transfer of Pilgrim License from Beco to Entergy ML20205L0301999-04-0909 April 1999 Notification of 990413 Meeting with Boston Edison Co & Entergy Nuclear Generation Co in Rockville,Md to Discuss Sale & Transfer of Pilgrim Station from Boston Edison Co to Entergy Nuclear Generation Co ML20196J5801998-12-0707 December 1998 Notification of 981209 Meeting with Representatives of Beco & Entergy in Rockville,Md to Discuss Sale of Pilgrim Plant ML20196F3461998-12-0202 December 1998 Forwards Info Re Operator Licensing Exam Administered on 981016-23 at Pilgrim Station,For Distribution Under Rids Code IE42 ML20196F5611998-12-0202 December 1998 Forwards Info Re OL Exam Administered on 981016-23 at Pilgrim Station,For Distribution Under Rids A070 ML20154G5141998-10-0202 October 1998 Notification of 981008 Meeting W/Beco in Rockville,Md to Discuss Core Spray Piping Integrity.Meeting Has Been Rescheduled to 981015 ML20154D5091998-10-0202 October 1998 Notification of Meeting W/Beco on 981008 in Rockville,Md to Discuss Core Spray Piping Integrity ML20247G2441998-04-15015 April 1998 Notification of Significant Licensee Meeting 98-34 W/Util on 980427 to Discuss Weaknesses in Licensee Alarm Assessment Program (EA 98-191) ML20203E2781998-02-19019 February 1998 Notification of Significant Licensee Meeting 98-18 W/Util in King of Prussia,Pa on 980310 Re Plant Design Basis Project Discussion ML20199C7581997-10-31031 October 1997 Notification of Significant Licensee Meeting 97-112 W/Util on 971113 to Discuss NRC SALP ML20212D6201997-10-28028 October 1997 Notification of Licensee Meeting on 971121 W/Util in King of Prussia,Pa to Discuss Apparent Violations Identified During NRC Insp 50-293/97-05 ML20140F6151997-06-11011 June 1997 Notification of 970612 Meeting W/Util in Rockville,Md to Discuss Net Positive Suction Head for ECCS Pumps ML20137Q9761997-03-31031 March 1997 Informs That as-found LOCA & Life Testing & Analysis Does Not Provide Acceptable Approach for Demonstrating Qualification at Accident Temp Higher than 340F,per 970110 TAR ML20137B4781997-03-14014 March 1997 Undated Memo Discussing Beco Reorganization ML20141A7361997-03-12012 March 1997 Rcommends That Key RES Staff Attend Subcommittee Meetings to Address Any Questions,Arise in Discussions Among Members & to Answer Any Key Questions Posed in Advance by Subcommittee Chairmen ML20149M3291996-11-12012 November 1996 Forwards Input Re TIA on Plant Licensing Basis & Subsequent Mod Under 10CFR50.59 for Two Safety Significant Problems ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20129D8331996-09-19019 September 1996 Notification of 961003 Predecisional Enforcement Conference 96-98 W/Util to Discuss Containment Penetration Protection. Meeting Closed to Public ML20134J7301996-07-26026 July 1996 Forwards Resolution of Spent Fuel Storage Pool Action Plan Issues Re Response to Two Postulated Event Sequences Involving SFP NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl IR 05000293/19930291993-11-23023 November 1993 Notification of Significant Licensee Meeting 93-156 W/Util on 931202 Re Three Recently Reported Design Issues in Insp Rept 50-293/93-29 ML20058C9711993-11-22022 November 1993 Notification of Significant Licensee Meeting 93-150 W/Util on 931217 Re Hpci/Rcic Reliability & Switchyard Betterment Status ML20059L9721993-11-12012 November 1993 Licensing Board Memorandum & Order Terminating Proceeding .* Informs That Time Provided by NRC Regulation to Review Decision of ASLB Terminating Proceeding in Docket Has Expired.W/Certificate of Svc.Served on 931112 ML20056C4721993-06-17017 June 1993 Discusses Util Assessment of Low Pressure Turbine Analysis. Licensee Retained Structural Integrity Assocs,Inc (SIA) to Evaluate Flaw Indications in 7GA Disk.Sia Anaylsis Reduce Some Obvious Conservatisms Used in GE Analysis ML20128F3911993-02-0303 February 1993 Requests Listed Instructions to Ensure That P Blanch of Northeast Utils & E Hadley of We the People Kept Promptly Informed of NRC Activities on BWR Water Level Indicators & Rosemount Transmitters ML20128E2181993-01-26026 January 1993 Notice of Significant Licensee Meeting 93-11 W/Licensee on 930225 in King of Prussia,Pa to Discuss Util Reorganization ML20059C1171992-11-20020 November 1992 Submits Status Rept on Reactor Water Level Spiking That Occurred on 921024.Related Info Encl ML20125D1161992-10-0707 October 1992 Notification of Significant Licensee Meeting 92-177 W/Util on 921217 to Discuss tie-in of New Security Computer ML20082B1581991-02-20020 February 1991 Summarizes Telcon W/R Murphy Re Mobilization Time for State of Ma Natl Guard Personnel Assigned to Respond to Wellesley, Ma Reception Ctr & State of Ma Civil Defense Agency Area II Headquarters in Event of Emergency at Facility ML20062H5361990-11-23023 November 1990 Forwards Info from Pilgrim Citizens Radiological Monitoring Network,Covering Rept Periods 900910-1017 ML20059P0861990-10-0101 October 1990 Notification of Significant Licensee Meeting 90-118 W/Util on 901016 to Discuss SALP ML20059L1541990-09-0707 September 1990 Notification of Significant Licensee Meeting 90-114 on 900912 at Region I Ofc to Discuss Corrective Actions & Restart Planning Re 900902 Manual Reactor Scram ML20059G4681990-08-0606 August 1990 Forwards Citizens Radiological Monitoring Network Weather Data Rept for Apr-Jul 1990 for Processing Through Nudocs Sys ML20127B4901990-08-0303 August 1990 Responds to 900726 Request for Recommendations for Appropriate Actions in Response to Inspector General Rept 90N-02 ML20127B4961990-08-0101 August 1990 Advises That Staff Did Not Conduct Thorough Review of Offsite Emergency Preparedness Which Resulted in Inaccurate Info Being Provided to Commission ML20058B4501990-06-28028 June 1990 Provides Status Rept Re Progress of off-site Emergency Preparedness Activities at Facility ML20055C2661990-02-0505 February 1990 Forwards Draft Ltr to Util Re Completion of Plant Power Ascension Program.Ltr Will Be Issued on 900209 Which Will Accept Util Completion of Power Ascension Program & Close Out Confirmatory Action Ltr CAL-86-10 ML20248C5841989-09-26026 September 1989 Notification of Significant Licensee Meeting 89-154 W/Util on 891006 in Plymouth,Ma to Discuss SALP Mgt ML20247N0121989-09-12012 September 1989 Forwards Plant Status Rept for 890826-0908.On 890830,reactor Automatically Scrammed Due to Fault on Main Generator Voltage Regulation Circuitry.On 890905,inadvertent Actuation LPCI Loop Select Logic Experienced ML20246N5751989-08-30030 August 1989 Forwards Plant Biweekly Status Rept for 890812-25 ML20245F6401989-08-0101 August 1989 Forwards Facility Biweekly Status Rept for 890715-28.NRC Restart Staff in Place & Onsite Monitoring Licensee Activities on Extended day-shift Basis During Reporting Period ML20247C0631989-07-19019 July 1989 Forwards Biweekly Status Rept for 890701-14.NRC Restart Staff in Place & Onsite & Monitoring Licensee Activities on around-the-clock Basis During Plant Startup & Power Ascension.Part 21 Related ML20247C1611989-07-14014 July 1989 Notification of Significant Licensee Meeting 89-112 W/Util on 890816 in King of Prussia,Pa to Discuss SALP ML20247E4531989-07-10010 July 1989 Forwards Plant Status Rept for 890617-30 Period.Rept Intended to Provide NRC Mgt & Public W/Overview of Plant Activities & NRC Restart Insp Activities ML20246K1141989-07-0303 July 1989 Notification of Significant Licensee Meeting 89-105/suppl Enforcement Conference Re Augmented Insp Team Findings Concerning 890412 Reactor Core Isolation Cooling Sys Overpressurization ML20245E6561989-06-22022 June 1989 Forwards Plant Biweekly Status Rept for 890603-16.On 890616, Reactor Operating at Approx 25% Power w/turbine-generator Synchronized to Grid.On 890612,util Commenced Controlled Reactor Shutdown to Perform Minor Mods,Maint & Testing ML20245F9581989-06-16016 June 1989 Notification of Significant Licensee Meeting 89-096 W/Util on 890619 in King of Prussia,Pa Re 890412 RCIC Sys ML20245A3311989-06-0909 June 1989 Notification of Significant Licensee Meeting 89-90 on 890627 W/Util in King of Prussia,Pa for Mgt Meeting to Discuss Status of Licensee Radiation Control Program ML20244E5081989-06-0707 June 1989 Forwards Biweekly Status Rept for 890520-0602.Rept Provides Overview of Plant Activities & NRC Restart Insp Activities. Part 21 Related 1999-08-18
[Table view] |
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NUCLEAR REGULATORY COMMi$$10N A
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4 NOV 195 Oocket No. 50-291 ..
MEMORANDUM FOR: Hugh L. Thompson, Jr. , Director Olvision of Licensing, NRR I FROM: Richard W. Starosteckt, Director !
Olvision of Reactor Projects, RI
SUBJECT:
LICENSING ACTION REVIEW FOR PILGRIM - PROPOSED REVISIONS TO TECHNICAL SPECIFICATIONS OF SURVEILLANCE INSTRUMENTATION (TAC #57510)
Region I has reviewed the Boston Edison Company's request dated April 12,.1985, I to change the calibration frequency for the reactor level, reactor pressure and i drywell pressure surveillance instrument channels in Technical Specification l Table 4.2.F from once per six months to each refueling outage. The licensee !
provided information to extend ihe frequency to once each 18 months.
Technical Specifications define refueling outage, for the purpose of surveillance inter-vals is a regularly scheduled outage unless the regularly scheduled outage i occurs within eight months of completion of a plant refueling outage. This definition as well as the schedules indicated in the Long Term Program issued ,
as Amendment 75 to the facility license, which defines the regularly scheduled '
outages, can exceed 18 months. The SE was written as agreed by the Project Manager, Paul Leech, based upon an 18 month calibration frequency in lieu of i the licensee's proposal for a refueling outage frequency. Therefore, the l licensee will need to modify their request for change in the calibration fre- ;
quency from once each refueling outage to once each 18 months. Enclosed is a -
modified technical specification page which describes the type of changes ,
needed to satisfy the SE. The Project Manager also agreed to obtain the :
licensee submittals to reflect the SE. As stated in the enclosed safety ,
evaluation, an 18 month calibration frequency change was found to be accept- '
able. The SALP input for TAC 57510 is enclosed.
This review also identified an apparent conflict in Table 4.2.F and the Standard Technical Specifications (STS). Specifically, the STS require an 18 month calibration frequency for the safety / relief valve position indicators, tcrus water level, and primary containment pressure; whereas, the Pilgrim 1 Technical Specifications specify each refueling outage. For the sama reasons c as stated above, each refueling outage can exceed 18 months. These sensors i provide similar surveillance information to those requested in TAC 57510. This l fact is provided for your information. l
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I CONTACT: Donald R. Haverkamp, RI (FTS 488-1236) [,
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! 8811160239 001010 I PDR FOIA '
JOHNSONOO-190 PDR l Hll l
i Memorandua for Hugh L. Thompson, Jr. 2 This review supersedes our prior licensing action review for Pilgrim forwarded I by letter Starosteckt to Thompson dated June 24, 1985 and completes the i requested Region ! a.ction for TAC 57510. The principal technical reviewers for :
this licensing action were Donald J. Florek and Ernesto C. Vanterpool, DRS.
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Richard W. tarostec\i, Director
( !
Division of Reactor Projects }
Enclosures:
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- 1. Safety Evt..uation Report .
- 2. SALP Input
- 3. Modified Technical Specification cc w/encis: I G. Lainas, AD/OR, NRR I J. Carter, TA, AD/OR, NRR l D. Vassallo, Chief, ORB-2, NRR l P. Leech, FM, ORB-2, NRR l
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ENCLOSURE 1
.. SAFETY EVALVATION SUPPORTING AMENOMENT NO. TO FACILITY OPERATING LICENSE NO. OPR-35 BOSTON EDISON COMPANY e PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Introduction and Background By letter dated April 12, 1985, (Reference 1), and letter dated ,
(Reference 2) Boston Edison Company (the licensee) proposed to amend its opera-ting license, OPR-35 by modifying the Ptigrim Nuclear Power Station Technical Specifications.
The proposal would change the calibration frequency for the reactor level, reactor pressure and drywell pressure surveillance instrument channels in Technical Specification Table 4.2.F from once every six months to once each 18 months.
The licensee, during a recent refueling cutage, replaced the existing GEMAC transmitters with Rosemount transmitters, Model Numbers 11520P and 1152GP.
This replacement was made because the GEMAC transmitters are obsolete and replacement parts are unavailable.
A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on May 21,1985 (50 FR 20970) for hearing and no pubite comments were received.
Evaluation The reactor level, reactor pressure and drywell pressure surveillance instru-l ment channels provide indication of plant status. The subject instruments do not provide any automatic actuation of safety systems, and therefore, the change does not affect any engineered safeguards actuation system (ESAS).
The surveillance requirements (SR) for the reactor level, reactor pressure, and drywell pressure surveillance instrument channels also include an instrument l check each shift, as specified by Technical Specification (TS) Table 4.2.F.
The instrument checks for the above surveillance instrument channels will remain unchanged by this amendment.
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Enclosure 1 2 The licensee's request for a decrease in the calibration frequency from 6 months to 18 months for the Rosemount transmitters is supported by the General Electric Licensing. Topical Report NEDO-21617-A, Class I dated December, 1978, "Analog Transmitter / Trip Unit System For Engineering Safeguard Sensor Trip Inputs". By letter dated June 27, 1978, the Commission reviewed and found the report acceptable for reference in license applications.
The NEDO-21617-A recommended frequency of calibration for these type transmit-ters is 12 to 18 months.
Based upon the al.ve, the staff finds that the proposed change to the subject technical specification calibration frequencies will not involve any pnysical change to the plant safety related systems, components or structures, will not increase the likelihooo of a malfunction of sTfety related equipment, will not increase the consequences of an accident prtviously analyzed, nor create the possibility of a malfunction different from those previously evaluated. The staff therefore finds the licensee's requestec change of calibration frequen-cies for the reactor level, reactor pressure aad drywell pressure instrument channels from once every 6 months to once each 18 months to be acceptable.
Environmental Consideration This amendment involves changes in the installation or use of a facility com-ponent located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements. The amendment also relates to a change in recordkeeping, reporting and administrative requirements. We have deter-mined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released of f-site, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a pro-posed finding that this amendment involves no significant hazards consideration and there has been no public comment on such findings. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
l Enclosure 1 3 m
I Referecces (1) Boston Edison Company letter W. D. Harrington to D. B. Vassallo, "Proposed i Technical Specification Change Calibration Frequency for Certain Rosemont ,
Transmitters". April 12, 1985.
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i (2) !
Principal Contributors: Donald J. Florek and Ernesto C. Vanterpool, r,1 vision I of Reactor Safety , i 0
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h Enclosure 2 '
SALP INPUT ON TAC #57510 Factitty: Pilgrim t Licensee: Boston Edison Company Docket: 50-293 l Request: Memorandurt Thompson to Starosteckt dated 4/12/85 g Functional Area: Licensing Activities ;
f Reviewer: D. Florek and E. Vanterpool The Itcensee was very responsive to requests for clarification of their pro-posal. Based on their request and clarifying information, it allowed prompt and efficient evaluation of the proposed change. Had the clarifying infor- l mation been included with the original proposal, no additional information t would have been required to evaluate the change.
Overall Conclusion - Category 1 s
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FNFS TAalz 4.2.F MINDRM 1T.ST AMD CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRIDENT{0_N Calibration Frequency Instrument Check Instrument Chaemel (B
- 1) Reactor Imvel Once s taaethe or kc d h4 Each Shift
- 2) anactor Pressure Once months .< Once < yed gc d Each Shift
- 3) Drywell Pressure Once/9Caonths .r dge Io{td C4ckt Each Shift Once/6 months Each Shift
- 4) Drywell Temperature once/6 asethe Each Shife
- 5) Suppression O. amber Temperature Scypression Osamber Water Lawel Once/6 monthe Each Shift
- 6) ,
MA Each Shift
- 7) Control mod Position
~
Neutros Moeitering (2) Each ShifC ,
8)
Once/6 monthe Each Shift k 9) Drywell/ Terms Differential Freneure E.
d Drywell Pressure Once/6 months Each Shift M g 10) (,g"Torue Pressure Once/6 monthe
,, U x D o Once each day Each refueling O
- 11) Safety / Relief Valve Fooition Indicator outaga [
(Primary / Secondary) e Once cach day 0
8' 12) Safety Valve Fooition Each refueling Indicator (Primary /
Secondary) outage as la~uns AMa s' M ies Mht 7td c
% N< ' 'N T.
M n k nt No. 48
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