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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8911999-10-15015 October 1999 Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20195K3071999-06-15015 June 1999 Forwards Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Plant ML20195K3851999-06-11011 June 1999 Forwards Copy of Notice of Consideration of Approval of Application Re Proposed Corporate Merger & Opportunity for Hearing.Application Seeks Approval of Proposed Indirect Transfer of FOL for Plant ML20196K9921999-06-0404 June 1999 Informs That NRC Ofc of NRR Reorganized Effective 990328.As Part of Reorganization,Division of Licensing Project Mgt Created ML20207E7351999-05-27027 May 1999 Responds to Requesting Reduction in IGSCC Insp Frequency Per GL 88-01 to Be Performed During Upcoming RFO 12.Forwards SE Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of H Water Chemistry ML20207B6341999-05-26026 May 1999 Informs That Licensee 990415 Submittal Re Financial Position of Entergy Intl Ltd,Llc Will Be Marked as Proprietary & Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act ML20207B7391999-05-24024 May 1999 Forwards from Kc Goss of FEMA to Cl Miller Forwarding FEMA Analysis of Prompt Alert & Notification Sys for Pilgrim Nuclear Power Station.Based on Review,No Significant Problems Exist with Alert & Notification Sys ML20207B0701999-05-24024 May 1999 Responds to Sent to Ofc of Congressional Affairs Requesting Info on Concerns Raised by One Constituent,J Riel Re Y2K Compliance of Pilgrim NPP in Plymouth,Ma ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206U7501999-05-17017 May 1999 Forwards Insp Rept 50-293/99-02 on 990308-0418.Two Severity Level 4 Violations Occurred & Being Treated as NCVs ML20206M1891999-05-11011 May 1999 Forwards SE of 980826 Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Sys Piping for Plant ML20206E0551999-04-29029 April 1999 Discusses Bulletin 96-03 Issued on 960506 & Beco Responses ,970207,981230,990121 & 990309 for Pilgrim Npp. Determined That Actions Taken Should Minimize Potential for Clogging of ECCS Suction Strainers ML20206B3031999-04-20020 April 1999 Forwards Insp Rept 50-293/99-01 on 990125-0307.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy.Security Program Was Also Inspected ML20205Q9491999-04-0909 April 1999 Informs That on 990225 NRC Staff Completed PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20205B9391999-03-24024 March 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure-Locking & Thermal-Binding of Safety-Related Power-Operated Gate Valves ML20204C7871999-03-17017 March 1999 Informs That Application Submitting Transfer of Facility Operating License & Matls License & Proposed Amend, Will Be Marked as Proprietary & Be Withheld from Public Disclosure Pursuant to 10CFR2.709(b)(5) ML20199K8321999-01-22022 January 1999 Forwards Request for Addl Info Re Transfer of Facility Operating License for Plant ML20199H5811999-01-20020 January 1999 Submits Exemption Withdrawal of 10CFR70.24(a) Re Criticality Accident Monitoring Requirements ML20198L7781998-12-22022 December 1998 Forwards Insp Rept 50-293/98-10 on 981020-1208.No Violations Noted.Nrc Regional Specialists Reviewed EP & Fire Protection Programs.Ep Program Was Found to Be Well Implemented ML20198J0891998-12-21021 December 1998 Forwards NRC Response to Me Lampert Re Transfer of Ownership of Pilgrim Station in Response to Senator Kerry Ltr Dtd 981019.NRC Will Terminate License Only When Licensee Remediates Site to Levels Specified in Regulations ML20198J1041998-12-21021 December 1998 Forwards NRC Response to Me Lampert Re Transfer of Ownership of Pilgrim Station in Response to Congressman Markey Ltr Dtd 981019.NRC Will Terminate License Only When Licensee Remediates Site to Levels Specified in Regulations ML20137T2211998-12-17017 December 1998 Responds to to Chairman Jackson Re Concerns About Possible Sale of Pilgrim Station & Waste Disposal Issues.No Application for License Received Nor Contract of Sale Between Beco & Entergy.Record Copy ML20198J1161998-12-17017 December 1998 Responds to to Chairman Jackson in Which Recipient Expressed Concern About Possible Sale of Pilgrim Station & About Waste Disposal Issues.Nrc Has Not Received Application for Transfer of License to Date ML20198P2781998-12-17017 December 1998 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety.App B Records Being Withheld in Entirety (Ref FOIA Exemption 4) ML20198B2021998-12-0909 December 1998 Advises of Planned Insp Effort Resulting from Licensee Irpm Review.Details of Insp Plan for Next 6 Months & Historical Listing of Plant Issues Encl ML20197H8521998-12-0909 December 1998 Responds to Ltr Sent to Chairman SA Jackson on 981028 Re Concern That NRC Will Not Perform Environ Assessment in Connection with Consideration of Approval of Transfer of License for Plants to Permit Sale ML20196J1201998-12-0404 December 1998 Ack Receipt of 971217 & 30 & 980112,0309,0423 & 0630 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-293/97-02,50-293/97-11,50-293/97-13, 50-293/97-80 & 50-293/98-01.Actions Found Acceptable ML20196B5421998-11-24024 November 1998 Forwards Plant SRO & RO Initial Exam Rept 50-293/98-301OL During Wk of 981016-23 ML20196F7631998-11-24024 November 1998 Forwards Insp Rept 50-293/98-203 on 980928-1023.No Violations Noted.Three Issues Identified Re Containment Flooding,Surveillance Testing Criteria & Protection for RBCCW System from High Energy Line Break Inside Drywell ML20196C1191998-11-20020 November 1998 Forwards Insp Rept 50-293/98-08 on 980907-1019.No Violations Noted.During Insp Period,Chemical Decontamination of Residual Heat Removal Sys Was Well Planned & Implemented Which Reduced Radiation Doses in Heat Removal Quadrants ML20195H7361998-11-16016 November 1998 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 981016 & 981019-23 at Facility.Nine Applicants Were Administered Exam & Nine Passed.Licenses Issued & Individual Test Results Encl.Without Encl ML20155C4781998-10-29029 October 1998 Forwards RAI Re Resoultion to GL 96-06 Issues at Plant,Unit 1.Response Requested by 981130 ML20154J7881998-10-0808 October 1998 Authorizes Mb Santiago to Administer Initial Written Exams to Applicants Listed (Except Applicants Redlined), on 981016.NRC Region I Operator Licensing Staff Will Administer Operating Tests During Week of 981019 1999-09-30
[Table view] |
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March 13, 1997 l
Mr. E. Thomas Boule'tte,; Ph.D .
J Senior Vice President -; Nuclear Boston Edison. Company Pilgrim Nuclear Power Station RFD #1 Rocky Hill Road Plymouth, MA 02360 j 1
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE PILGRIM NUCLEAR POWER l STATION TO CREDIT CONTAINMENT OVERPRESSURE IN THE NET POSITIVE SUCTION HEAD ANALYSIS FOR THE EMERGENCY CORE COOLING PUMPS (TAC NO.
M97789)
.l
Dear.Mr. Boulette:
j
~
Enclosed is a request for additional information (RAI) generated as a l result of NRC staff reviews, regarding your subject submittal dated January 20, 1997. The RAI includes three enclosures representing questions from l different areas of review. -The staff requests that the response be provided as soon as possible as this is a restart issue.
Sincerely, 1
(Original Signed By) l Alan B. Wang, Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-293 .
Request for Additional i
Enclosures:
Information -
gg Q%
cc w/encls: See next page .
Distribution: 1
- r. . f Docket File -Slittle * -
lf PUBLIC' , AWang I
l SVarga. ,
., ACRS ,
,m JZwolinski ,
, RConte, RI ,
PMilano ,
DOCUMENT NAME: G:\ PILGRIM \M977'89f '
- Ta receive e copy of this document,Indioote in the box: ,",C* = Copy without enclo'aureg CE* = Copy with enclosures *N' = No copy 0FFICE PM:PDI-3 l LA: POI-OLl (A)D:PDIrQ/VU l l NAME AWang MV Slitt W ~ PMil ano (/*U/'
DATE 03/lh/97 03/LS/97 03// 9/97 / 03/ /97 03/ /97 0FFICIAL RECORD COPY 9703170137 970313 PDR ADOCK 05000293 P PDR
pn natoq
," p t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30ess-4001
% ,,, ,, # March 13,1997 Mr. E. Thomas Boulette, Ph.D Senior Vice President - Nuclear Boston Edison Company Pilgrim Nuclear Power Station j RFD #1 Rocky Hill Road j Plymouth, MA 02360
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE PILGRIM NUCLEAR POWER STATION TO CREDIT CONTAINMENT OVERPRESSURE IN THE NET POSITIVE SUCTION HEAD ANALYSIS FOR THE EMERGENCY CORE COOLING PUMPS (TAC NO.
- M97789)
?
Dear Mr. Boulette:
! Enclosed is a request for additional information (RAI) generated as a
! result of NRC staff reviews, regarding your subject submittal dated January ,
j 20, 1997. The RAI includes three enclosures representing questions from
! different areas of review. The staff requests that the response be provided l
! as soon as possible as this is a restart issue.
Sincerely, A he 7 l Alan B. Wang, P' ject Manager i Project Directorate I-3
- Division of Reactor Projects - I/II j
Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
Request for Additional Information 1
cc w/encls: See next page l
i l
- i 5
Pilgrim Nuclear Power Station
! cc:
l Mr. Leon J. Olivier Mr. Jeffery Keene
- Vice President of Nuclear Licensing Division Manager i Operations & Station Director Boston Edison Company l Pilgrim Nuclear Power Station 600 Rocky Hill Road IFD #1 Rocky Hill Road Plymouth, MA 02360-5599 i i Plymouth, MA 02360 i Ms. Nancy Desmond j Resident Inspector Manager, Reg. Affairs Dept.
U. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station
- Pilgrim Nuclear Power Station RFD #1 Rocky Hill Road
! Post Office Box 867 Plymouth, MA 02360 )
j Plymouth, MA 02360 '
i Mr. David F. Tarantino j Chairman, Board of Selectmen Nuclear Information Manager
( 11 Lincoln Street Pilgrim Nuclear Power Station 4 Plymouth, MA 02360 RFD #1, Rocky Hill Road 4 Plymouth, MA 02360 l
! Chairman, Duxbury Board of Selectmen l Town Hall Ms. Kathleen M. O'Toole
! 878 Tremont Street Secretary of Public Safety i Duxbury, MA 02332 Executive Office of Public Safety j One Ashburton Place
- Office of the Commissioner Boston, MA 02108
{ Massachusetts Department of i Environmental Protection Mr. Peter LaPorte, Director One Winter Street Attn: James Muckerheide Boston, MA 02108 Massachusetts Emergency Management Agency Office of the Attorney General 400 Worcester Road
- One Ashburton Place P.O. Box 1496 1 20th Floor Framingham, MA 01701-0317 i Boston, MA 02108 i Chairman, Citizens Urging i Mr. Robert M. Hallisey, Director Responsible Energy j Radiation Control Program P.O. Box 2621 l Massachusetts Department of Duxbury, MA 02331 1 Public Health
( 305 South Street Citizens at Risk j Boston, MA -02130 P.O. Box 3803
- Plymouth, MA 02361 i Regional Administrator, Region I U. S. Nuclear Regulatory Commission W.S. Stowe, Esquire 475 Allendale Road Boston Edison Company i King of Prussia, PA 19406 800 Boylston St., 36th Floor
+
Boston, MA 02199 i Ms. Jane Fleming 4
8 Oceanwood Drive i Duxbury, MA 0233 i
s i
i 1
l cc: (cont.)
Chairman Nuclear Matters Committee Town Hall 11 Lincoln Street Plymouth, MA 02360 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company ,
P.O. Box 426 j Ludlow, MA 01056-0426 l
l
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I I
1 i
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Request For Additional Information Pilgrim Credit for Containment Overpressure in NPSH Calculations
{
i 1. By letter dated January 20, 1997, Boston Edison Com)any (BECo) submitted
! a request for NRC review. The ' deco letter states tiat "there is a
- question, from a licensing standpoint, whether credit for containment ;
- 3ressure as part of the net positive suction head (NPSH) calculation can 1 i >e taken under the 10CFR50.G process or whether NRC review is j needed..... we are requesting NRC review and approval of this issue prior
- to March 15, 1997." Additionally, the letter requests "NRC review and i approval of the wording currently in FSAR rev.19 section 15.3.1.3."
Credit for containment overpressure can be taken as part of the NPSH calculation if the credited overpressure is specified in the plant's licensing basis. The staff contends that Pilgrim's current licensing i
- basis is that no containment overpressure is required for adequate NPSH i of the emergency core cooling system (ECCS) pumps with clean strainers.
!- With the changeout of insulation in 1984, BEco cannot assume that their
! ECCS strainers will be clean following a design basis loss-of-coolant
- accident (LOCA), therefore, Pilgrim is outside their current licensing
- basis. BEco should be proposing a licensing basis change in order to i resolve the USQ regarding containment overpressure and debris laden ECCS
- strainers. Alternatively, submit information including pump l manufacturers test data or other test data to demonstrate that the i performance of the ECCS pumps while cavitating (i.e., with inadequate
! NPSH) would be adequate to fulfil their safety functions for the limiting i accident conditions.
i 2. Page 17 of SE 2983 states that the utlimate heat sink (UHS) temperature l selected for the design rating of safety related heat removal systems and
, equipment is 65 *F whereas the UHS temperature for the design rating of
! the main heat sink and associated equipment required for power generation is 75 *F. This implies that the safety related heat removal systems and
. equipment are not designed to perform their intended function during the i j warmer summer months. Furthermore, a result of the in-depth analysis of ;
the UHS temperature indicated that the 75 *F SSW inlet temperature could
? be exceeded on occasion for a limited amount of time. If 75 *F is an upper-bound for the UHS, provide an explanation as to why the safety ;
i related heat removal systems are not designed for the upper-bound r temperature. Also, page 2 of SE 2983 states that the 75 *F SSW injection 1 temperature analysis will supplement rather than replace the current l analysis. The staff believes that the upper-bound 75 *F temperature i should replace the current 65 *F analysis. Provide justification for l supplementing the current 65 *F analysis rather than replacing it. ;
- 3. Pilgrim does not have a TS limit on the UHS temperature, and thus no Limiting Condition for Operation actions need to be taken if the UHS temperature exceeds the safety related heat removal systems design rating (65 *F) or the main heat sink design rating (75 "F). Describe Pilgrim's current procedures that are in place for GHS temperatures greater than 65'*F and 75 *F. Has Pilgrim considered adopting a Technical Specification limit on UHS temperature 7 ENCLOSURE 1 l
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- 4. Page 20 discusses removing the reference to local pool temperature limits i and the reference to the associated 160 *F bulk suppression pool i
temperature limit from Technical Specification Bases 3/4.7.A. However, TS Surveillance Requirements 3/4.7.A.c still references the 160 *F bulk suppression pool temperature. Will a TS amendment be requested to make
] the TS surveillance requirements consistent with the TS bases?
4 i 5. Page 21 of SE 2983 states that the Chapter 14 design basis LOCA analysis based on a 65 *F SSW inlet temperature assumed that at 600 seconds, one RHR pump is shutoff and the RHR loop is placed in suppression pool i
cooling (with or without spray). However, the design basis LOCA analysis l
' performed using a 75 *F SSW inlet temperature assumed that at 600 seconds, LPCI with heat rejection mode, with two RHR pumps in operation is placed in service and the heat exchanger bypass valve in its full open normal position. This continues until 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> post LOCA when transition i to LPCI with heat removal using one RHR occurs. Based on this i description, the 75 *F design basis LOCA is more limiting than the 65 *F i design basis LOCA. Do the Emergency Operating Procedures accommodate the i
' differences in pump operation for the two SSW temperature cases?
i i 6. Provide Reference 22, GE-NE-T23-00732-01, " Pilgrim Nuclear Power Station Containment Heat Removal Analysis," March 1996, (SUDDS/RF96-05, Rev.0),
which performs the design basis LOCA analysis using 75 *F SSW inlet i temperature.
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!- 7. Pages 26 and 27 of SE 2983 discuss the ECCS NPSH calculations for the two i design basis LOCAs. FSAR Figures 14.5-10 and 13 and Figures 14.5-18 and ,
i 19 depict the NPSH availability for RHR and Core Spray pumps with leakage i effects included for the 65 *F and 75 *F SSW inlet temperatures,
- respectively. The licensee evaluated the potential effect of insulation
- debris accumulating on the ECCS strainers and concluded that the
) increased suction head loss from the debris is within the margin for NPSH l
available to the ECCS pumps. The staff notes that the FSAR figures j depict the licensee's calculated NPSH margin based on clean strainers.
Debris on the ECCS strainers reduces the NPSH available and this fact
- should be depicted on the FSAR figures. Additionally, the staff notes that the margin depicted on the FSAR figures are not the licensing basis l margin. Credit for the margin above atmospheric pressure entails i
- changing the licensing basis margin.
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l 8. Page 2 of letter dated January 20, 1997, E. T. Boulette to the NRC, a states that with the maximum det ris loading, a torus airspace pressure of ,
- approximately 4.1 psig is required at the peak suppression pool l
- temperature of 178 *F to provide the required NPSH for both the RHR and '
l CS pumps. Using Pilgrim's calculation M-662, the staff calculated that
- 3.6 psig is required for the 8.6 feet of head loss due to the maximum l debris loading. Provide the details of the calculation for the required ,
! containment overpressure for adequate NPSH at the peak suppression pool I temperature of 178 'F.
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- 9. Upon review of the Pilgrim FSAR, the staff noted that theie are two sections 14.5.3.1.3, Core Standby Cooling System Pump Net Positive Suction Head; one which begins on page 14.5-10 and one on page 14.5-11.
It appears that the first section 14.5.3.1.3 was for the 65 *F salt i
service water case; however, the 75 *F salt service water case is i
discussed in the last three paragraphs of this section. The second section 14.5.3.1.3 discusses both the 65 *F and the 75 *F SSW injection temperature cases. Which section 14.5.3.1.3 is the applicable section for the design basis net positive suction head calculation? Provide an i explanation as to why the 75 *F SSW injection case does not bound the j 65 *F SSW case.
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- 10. Page 14.5-12b of the FSAR, part of the second section 14.5.3.1.3, discusses NPSH available under RCIC operation. Based on the model assumptions and the NPSH required, i.e., 28 ft, this part of the FSAR is not consistent with the new 65 *F and 75 *F NPSH analyses. Was NPSH reanalyzed for these two cases under RCIC operation?
- 11. SE 2983 evaluates the changes to the local pool' temperature limits, design basis LOCA analysis, FSAR steam line break analysis, Appendix R fire events, ATWS, station blackout, containment metal-water reaction ,
capability, ECCS NPSH, suppression pool temperature, component cooling, building compartment cooling, environmental qualification, standby gas treatment, standby AC power sources, and piping design due to the increased SSW inlet temperature of 75 *F. According to SE 2983, new analyses were performed to verify that the increase of SSW inlet temperature is within the design basis of the affected systems. It is not clear to the staff that the increase of SSW inlet temperature is within the design basis of the affected systems and that the increase in temperature will not increase the consequences of an accident previously evaluated in the FSAR. Provide a discussion as to why the increase of service water temperature is not an unreviewed safety question.
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j Request for Additional Information
- 1. SE 2971: a) How was the suppression pool temperature profile, used to determine the containment pressure, calculated? Specify what code was f, used.
! 2. SE 2971: Why was SHEX NOT used to compute the pressure for SE 29717 Explain why you believe the ideal gas formulation for the noncondensables is adequate, versus use of a computer code. Discuss the
- conservatism /nonconservatism of the method you have used, as well as any other differences between the two methods.
I 3. SE 2971: Does SE 2971 describe the current design basis for ECCS pump NPSH7 If not, what is the current design basis? In particular, does it l assume 65 'F seawater temperature or 75 *F seawater temperature and
- strainer clogging? How much overpressure is needed? The staff needs to i know explicitly the design basis regarding NPSH for the RHR and CS pumps,
! including the codes and assumptions used to calculate the containment j pressure for NPSH purposes,. State how calculation M662 ties in with SE
! 2971 and 2983.
l 4. Calculation M662: 'In calculation M662, initial wetwell airspace pressure is given as 0.5 psig on sheet 6 of 84, whereas it is given as 0 psig on
{ sheet 15 of 84. Which value is actually used?
E i 5. Calculation M662: In Table 8 of calculation M662, the wetwell free
. volume in the Amendment 9 column is given as 120,000 cu. ft., whereas in
. the more recent analyses given in the other columns it is given as i 124,500 cu. ft. Why are these different?
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- 6. Calculation M662: In Table 8 of calculation M662, in the 65 and 75 deg F l columns for initial drywell relative humidity, the relative humidity is i given as 80%, versus 100% in the Amendment 9 column. 80% seems less i conservative from a minimum pressure perspective, since it tends to i
increase noncondensables in containment, resulting in a higher, not minimum, containment pressure. '
i l Discuss why this apparently non-conservative change was made in the i relative humidity.
. 7. Calculation M662: In calculation M662, discuss more fully the effect of 1 an initial drywell temperature of 150 deg F versus 135 deg F, and the j rationale for choosing 150 deg F.
, 8. Calculation M662: In calculation M662, you assume that the steam space pressure of the containment atmosphere cancels with the vapor pressure of the suppression pool; i.e., they are both saturated. This is dependent on'the mixing assumptions between the atmosphere and pool. What
- assumptions are made in the SHEX code (e.g., complete mixing, water falls j directly to pool, etc.)?
i ENCLOSURE 2 i
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- 9. Calculation M662: Provide a discussion of the differences between the input parameters in the benchmark and revised analyses given in Table 4 of ':lculation M662. Discuss any differences in the results, and in i
pas ticular, discuss the effect of differences in input parameters on the calculated results.
- 10. SE 2983: What is the rationale for choosing 1.3 psig initial pressure in the drywell and 0.0 psig in the wetwell, versus assuming 0.0 psig (i.e.
i atmospheric) in both the drywell and wetwell? What are the normal
{ operating conditions in the drywell and wetwell?
- Does 1.3 psig in the drywell tend to help minimize the containment j pressure response, or would a lower initial pressure be more suitable for
- the minimum pressure calculation necessary for NPSH overpressure
, calculations?
- 11. Which GE code is used in the decay heat analyses?
- 12. List and justify the changes in input parameters used in the ANS 5.1 decay heat curve versus those used previously in the May-Witt analyses.
- 13. Provide and justify the values for the following ANS 5.1 input parameters:
- a. Q (total recoverable energy) (MeV/ fission).
- b. SQ (one standard deviation of recoverable energy, Q) (MeV/ fission)
- c. P (total power from fissioning of one nuclide) (MeV/sec)
- d. 6P (one standard deviation of power, P, from fissioning of nuclide)
(MeV/sec)
- e. Fractional fission product power for: U235, U238, Pu239 and Pu241
- f. R-factor (the actinide production multiplier)
- g. G-factor (a decay heat multiplier to account for the effect of neutron capture in fission products)
- h. Si (a multiplier applied to the G-factor equation) (fissions per initial fissile atom)
- 1. Power history (length of full-power operation before shutdown)
- 14. Specify how the length of time at full power operation befoie shutdown was estimated, and confirm that this value is 3.4 years, as specified in GE Report GE-NE-T23-00732-01, " Pilgrim Nuclear Power Station Containment Heat Removal Analysis," March 1996.
- 15. Were the contributions to the total decay heat from U-239 and Np-239 calculated in accordance with Branch Technical Position ASB 9-27 If not, provide the equation used to calculate them, and comment on the differences between it and the models given in position ASB 9-2,
- 16. Justify that your use of the ANS 5.1 model for decay heat is conservative by showing that at least two standard deviations of confidence in your analyses results is provided.
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.e Request for Additional Information
- 1. On page 14 of 84 of calculation M-662, there is an equation 10 which provides the maximum allowable suction line pressure loss. This equation includes a net positive suction head margin (NPSHM) term which inappropriately increases the allowable suction line loss. Also, the i
' NPSHM term has nothing to do with possible piping obstruction degradation l and increase in suction line pressure loss from the appropriate test ;
a reference value for the test flow. Should the suction line pressure loss
- calculation be modified?
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i ENCLOSURE 3