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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10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses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 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) ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) 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 ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing 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 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 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) 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 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 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 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 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 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 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 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
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A r
FEB 041993 ,
Docket No. 50-293 Mr. Paul hi. tilanch 135 flyde Road West llartford, Connecticut 06117
Dear Mr.111anch:
In responst u your request for t'.pdated information on reactor vessel instrumentation issues at Pilgrim, enclosed is relevant information from our inspection conducted in December 1992.
This is essentially the same information which was provided to you in our letter of January 7, 1993.
If we can be of further assistance, please contact Mr. IIugene Kelly of my staff at (215) 337-5183.
Sincerely, ,
Original Signed By:
hees C. linyllie t
James C. Linville, Chief Projects Isranch No. 3 Division of Reactor Projects
Enclosure:
NRC Inspection Report 50 293/92 28 (Section 8.3) cc w/ encl:
Ernest C. fladley, Esquire cc w/o encl:
Public Document Room (PDR)
Local Public Documen: Room (LPDR)
Nuclear Safety information Center (NSIC)
NRC Resident inspector 9302190050 930204 POR ADOCK 05000293 G PDR i
I OFFICIAL RECORD COPt L , . _ . . _
i Ium um14 4 Mr. Paul M. Illanch 2 FEB 041993 ,
bec w/o encl:
G. Kelly, DRP J. Linville, DRP J. Macdonald, SRI - Pilgrim x
1:DRP RI:Dy$'
(
Tm(eA L le, 2/2/93 g )
OFFICIAL RECORD COPY A:PilLANCli.MEO
- Y f * * %c UNiiln LT Alls a' f4
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g> ( e Nucit: AH H[GUl.ATORY COMMISSION m onin g ;e4 y [ 41b tilll NDAl f itOAD s- , ~. o, . sm n ,ms.,, ,m ,m
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Docket No. $0 293 2 8 $3 Dr.11. Thomas Ikiulette Acting Senior Vice President-Nuclear lloston Edison Comjuny Pilgrim Nuclear Power Station RFD #1 Rocky liill Road Plymouth, hiassachusetts 02360
Dear Dr. Ikiulette:
SUluliCT: PILGRlhi INSP11CTION 92-28 This refers to the safety inspection conducted by hiessrs. J. hiacdonald, A. Cerne, and D. Kern of this office November 24 to December 31, 1992 at the Pilgrim Nuclear Power Station, Plymouth, hiassachusetts. Areas relevant to the health and safety of the public examined during this inspection are described in the enclosed report. Our findingr, were based upon observations of performance and independent evaluations of safety systems and quality records. The preliminary results have been discussed with hit. L. Schmeling and other members of your staff at the conclusion of the inspection period.
Good precautionary measures were taken during the storm on December 11 14, that included reduced reactor power operations. Your operating staff's response to the weather induced automatic reactor trip was prompt, particularly the shift supervisory oversight of trip recovery activities and electrical distribution system status, llased on the results of this inspection, certain of your activities appeared to be in violation of NRC requirements, as specified in the enclosed Notice of Violation (Notice). It appears that several opportunities existed (but were missed) as part of supenisory procedure review, incident critique, and post-trip report processes to identify the improperly established main steam line (htSL) high radiation alarm setpoint prior to reactor startup. Setting of the alarm was of minor safety significance in that the reactor protection system function is independent of the alarm.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response, in accordance with 10 CFR 2.790 of the NRC's
" Rules of Practice,* a copy of this letter and its enclosures will be placed in the NRC Public Document Room. The responses directed by this letter and the enclosed Notice are not subject to the clearance procedures of the Office of hianagement and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No. 96.511.
l--
JAN 2 8 Y393 Dr. li Thomas Ikmlette 2 Your cooperation with us is appreciated.
Sincerely, g bh/t ames Linville, Ch'-
Projects Branch N . 3 Division of Reactor Projects
Enclosures:
- 1. Notice of Violation
- 2. NRC Inspection Report No. 50-293/92-28 cc w/encis:
E. Kraft, Acting Vice President, Nuclear Operations and Station Director L. Schmeling, Plant hianager V. Oheim, Manager, Regulatory Affairs and Emergency Planning Department D. Tarantino, Nuclear Information Manager N. Desmond, Compliance Division Manager R. Itallisey, Department of Public Ilealth, Commonwealth of Massachusetts R. Adams, Department of Labor and Industries, Commonwealth of Massachusetts Tne lionorable Edward M. Kennedy The lionorable John F. Kerry The lionorable Edward J. Markey The lionorable Terese Murray The lionorable Peter V. Forman B. McIntyre, Chairman, Department of Public Utilities Chairman, Plymouth Board of Selectmen Chairman, Duxbury Board of Selectmen Plymouth Civil Defense Director Paul W. Gmmer, Massachusetts Secretary of Energy Resources Sarah Woodhouse, legislative Assistant A. Nogee, MASSPIRG Regional Administrator, FEMA Office of the Commissioner, Mase.husetts Department of Environmental Quality Engineering Office of the Attorney Ocneral, Commonwealth of Massachusetts T. Rapone, Massachusetts Executive Office of Public Safety Chairman, Citizens Urging Responsible Energy .
Public Document Room (PDR) 12 cal Public Document Room (LPDR)
Nuclear Safety Information Center (11 SIC)
K. Abraham. PAO (2 copies)
NRC Resident inspector Commonwealth of Manachusetts, SLO Designee l
U.'S. NUCLEAR REGULATORY COMMISSION.
REGION I Docket No.: 50-293 Report No.: 92-28 Licensec: Boston Edison Company .
800 Boylston Street Boston, Massachusetts 02199 Facility: Pilgrim Nucicar pewer Station laation: Plymauth, Massachusetts Dates: November 24 - December 31,1992 Inspectors: J. Macdonald, Senior Resident inspector A. Cerne, Resident inspector D. Kem, Resident I c.pecto M' ! [
Approved by:
E. Kelli, C;d f, Reactor Pr ccts Section 3A ' Date Scope: Resident inspection addressed the areas of plant operations, radiological controls, maintenance and surveillance, emergency preparedness, security, safety assessment and quality verification, and engineering and technical support.
Initiatives selected for inspection included: restoiation from an electrical backfeed lineup; observation of an inplant emergency preparedness drill; control and testing of certain containment isolation valves; and, plant design changes associated with the reactor vessel head spray lines, inspections were performed on backshifts during November 30 and December 1 4, 7,11,13-18, and 21-31,1992. " Deep" backshift inspections were performed on December 13 from 10:00 to 12:00 p.m. and December 14 from 00:01 to s 05:45 a.m.
Findings: Inspection results are summarized in the Executive Summary.
Procedure 3.M.2-7.6, "NUMAC Img Radiation Monitor Setpoint Change Procedure" was not properly performed 'lechnicians established incorrect RPS protective setpoints and management reviews failed to identify the associated discrepancies (Violation 92-28-01, see Section 4.4).
The technical basis for the deactivation of a head spray line remains unresolved (Unresolved item 92-28-02, see Section 8.2).
DOde i 1
t - - - - - - _ _ _ - _ _ _ _
EXECUTIVE SUMM ARY Pilgrim luspection Report 50-293/92-28 Plant Operations Operations Section preparation for and response to the effects of a northeaster storm were comprehensive. Decisions to maintain reduced reactor power at the 80% rod pattem line and to separate the safety-related buses from the distribution system deraonstrated a strong safety perspective.
The immediate response by operators to two automatic reactor trips was appropriate.
Communications, use of procedures, and supervisory oversight of control room operations were excellent during post-trip recovery activities and subsequent reactor startups.- Also, the identification of loose or missing bolts on motor operated valve actuator limit switch covers during routine rounds indicated good questioning attitudes and attention to detail by plant .
operators.
Maintenance and Surveillance Actions taken to verify the presence of and trend the effect of-steam leakage past safety relief valve (SR*A RV 203-3A were thorough, Although not required by Technical Specifications (TS), the decilian to establish cold shutdown and replace the leaking SRV pilot valve following an unrelated pw shutdown demonstrated sound safety judgement.
In addition, coordination between the materials & component engineering section, maintenance personnel, and system engineers to complete the repair during this unscheduled maintenance period was outstanding. Restoration from the backfeed electrical lineup following post trip ;
corrective maintenance was performed. Maintenance and operations personnel demonstrated excellent procedural knowledge and communications.
An automatic reactor trip on December 20 was caused by procedural weaknesses and poor work practices by technicians changing the main steam line (MSL) high radiation protective setpoints.
Alsc, the technicians failed to lower the MSL high radiation alarm setpoints following the reactor trip. As a result, the MSL high radiation alarm was not avas.ble to control. room operators upon the subsequent plant restart. Failure to properly reestablish the MSL high -
radiation protective setpoints and associated failure of the management review process on two-occasions indicates a need for greater management attention.
Emergency Preparedness The .apability to draw, analyze, and provide real time post-accident sampling system data under simulated emergency conditions was successfully demonstrated in a December drill, Safety Assessment and Quality Verification Implementation of Phase II of a planned three phase structural reorganization, to become effective January 1,1993, was announced on December 16, 1992. Licensee event reports (LERs) were of good detail, accurate, and clearly identified root cause and corrective action, detailed and properly addressed the required reporting criteria, ii
(EXECUTIVI: SUMM AltY CONTINUED)
Engineering and Technical Support Deactivated head spray line containment isolation valves "
remain to be removed from the Type C local leak rate test program. Several questions regarding -
American Society of Mechanical Engineers (ASME) Code criteria and the technical basis of certain aspects of the head spray line deactivation plant design change remain unresolvedi Continuing NRC review of the licensee reactor vessel water level instnamentation spiking status ,
determined the operability assessment was consistent with the guidance of NRC generic documentation for degraded or nonconforming conditions on operability.
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14 The inspector also checked the compatibility of the Residual Heat Removal (RHR) system configuration, as-left after .nplementation of PDC 86-20 with the design intent of PDC 86-528-196 and, in this regard, additionally reviewed drawings M100BC-282-1, h1100-38-7, hilN 40-12, hi241 and an earlier FRN 191 to PDC 86-52B. During a plant in pection tour, the inspector noted that the electrical supply breaker (B20B3) for the head spray valve (610-1001-63) which had been removed during RFO 8 was still danger-tagged open. The inspector reviewed the PNPS tagout sheet '190-10-21 and determined that this open tag status was inconsistent with the handling of the electrical supply to the other head spray CIV (hiO-1001-60), where the breaker had been left open, but the tagout cleared. The inspector discussed this inconsistency with cognizant plant personnel who initiated action to query the nuclear engineering department as to whether the entire tagout 'I90-10-21 could be closed and cleared.
In review of PDC 86-52B-196 design change criteria, the inspector identined a statement which implied that the abandoned piping in the reactor head spray system outside containment would remain vented. However, since PDC 86-20 installed a pipe cap on one side of this piping and PDC 86-52B-196 capped the piping at penetration X-17 on the other side, the reviewed licensee documentation provided no indication how such venting was implemented in that the valves identiGed in the PDC relating to this piping appeared to have been left in the closed position.
Furthermore, since valve hiO-1001-60, as identified in tagout '190-10-21 was chained closed, two vent paths, one on either side of the closed valve, would have to have been provided for the as-left piping to be consistent with the PDC design criteria.
Additionally, the inspector con 6rmed that the pipe cap for the penetration X-17 piping had been procured to AShiE Code,Section III, Class 2 criteria as " impact-tested material." However, it appeared that an impact-tested weld procedure had not been used to install the pipe cap as would be required by the AShiE Code,Section IX, unless certain conditions of exemption allowed by Section 111 of the code were satis 6ed. Given that the PNPS FSAR documents the containment drywell shell material to be fabricated of impact tested plate and forgings, the licensee issued problem report 93-9005 to resolve this question regarding the weld procedure quali0 cation.
l The inspector determined through the review of PDC 16-52B-196 and related supporting documentation that the current configuration of the reactor head spray piping was acceptable, in that the continued safe operation of PNPS had not been adversely affected by the design l modification. However, as noted above, certain questions, regarding the existing pipe venting i
and the containment penetration weld quali0 cation criteria, remain open. Pending the licensee presentation of evidence that the installed configuration is in compliance with the intended PDC design criteria, these issues remain unresolved (92-28-02).
8.3 Reactor Vessel Water Ixvel Instnamentation Update NRC Inspection Report 50-293/92-23, Section 8.1, provided a detailed status of licensee activities in response to reactor vessel water level instrumentation spiking e perienced during
- recent reactor shutdown evolutions. Specifically, the issue has been addressed in terms of the
! generic concern for level instrumentation inaccuracies during rapid depressurimtion events due m the evolution of noncondensible gases from the reference legs.
15 The NRC conducted review of BECo operability determination of the level instrumentation', with particular attention on the instrumentation associated with the two-thirds (2/3) core height containment spray interlock. The safety function of this instrumentation is to provide level-signals and indication such that adequate core cooling can be achieved for certain classes of accidents. The NRC staffindependently concluded that this safety function would be satisfied at Pilgrim based upon the following:
- If flow is diverted to containment spmy after 2/3 core coverage is achieved, one core spray pump alone is adequate to maintain 2/3 level and core cooling. Thus, even the diversion of all available low pressure coolant injection (LPCI) would not preclude adequate core cooling.
- It is unlikely that signincant diversion of flow would occur prior to reflooding the vessel to 2/3 core height, because:
-- the interlock does not cause any automatic actuations; that is, satisfying the interlock does not automatically divert LPCI flow to containment spray.
-- according to the Pilgrim Reload Analysis (S AFER/GESTR Report NEDC-31852),
for desi3n basis loss of coolant accidents, the core is reflooded to 2/3 core height within approximately 60 to 150 seconds; therefore, the operator would have to immediately divert LPCI for such erroneous action to occur prior to reflooding the vessel. Moreover, operators are directed by procedure to assure adequate core cooling prior to initiation of containment spmy, and operators have been sensitized to potendal errors in level indication. Station Emergency Operating Procedures (ie, EOp-03, " Primary Containment Control") which govern the decision to divert LPCI flow and spray the containment would require the presence of a high drywell pressure above 2.5 psig. Also, the EOPs direct that only "those RHR pumps not required to assure adequate core cooling by continuous operation in the LPCI mode" be used for containment spray diversion.
-- over 20 linear feet of reference leg volume, including both horizontal and vertical-sections, must be voided and not recovered at Pilgrim to cause a continuous 14 inch level error, and an error of this amplitude is already considered in the interlock setpoint.
- it is expected that the magnitude of error in the level indication following an actual depressurization event would - be significantly less than that estimated by_
conservative assumptions used in the calculations performed by the General Electric Company and the BECo consultants.
- the potential for level errors has likely been lessened by actions taken by the licensee to reduce external reference leg leakage (ie, tighten fittings and packing at the instrument racks).
- Ifit was postulated that LPCl now was prematurely diverted to containment spray, the safety function of the interlock would still be fulfilled, because:
16 at Pilgrim the diversion of LPCI now to containment spray (both drywell and toms) represents only approximately 25% of the capacity of one LPCI/RHR pump.
- Appendix K analysis from the current Pilgrim Reload Analysis for the most -
limiting case for which LPCI flow is credited (ie, battery failure case), indicate a 1694 degrees F peak clad temperature (PCT), which represents a 506 degrees F margin to the 2200 degrees F PCT limit.
- NRC staff reviewed analysis for a similar BWR/3 plant in which 100% of the flow of one RHR pump was assumed to be diverted from the core from the onset of the accident. These analysis support the staff judgement that, using Apgndix K analysis assumptions, diversion of 25% of the flow of one RHR pump would not result in exceeding 2200 degrees F PCT.
Based on the above, the NRC staff concluded that any manual actuation of containment spray which is based upon an erroneous level signal to this interlock is both highly unlikely and of low safety significance, and that the safety function of the level instrumentation system at Pilgrim would therefore be fulfilled. The NRC staff also concluded that the BECo operability determination was performed consistent with the guidance of NRC Generic letter No. 91-18, "Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability," dated November 7,1991.
During reactor depressurization following the two automatic trips that occurred during this inspection period, no reactor vessel water level instrumentation " spiking" was observed. The reactor tripped on December 13,1992, after 20 days of operation and again on December 20,1992, shortly after startup from the previous trip, The NRC will continue ~to monitor 'BECo's progress in resolving the problem of noncondensible gas accumulation in the level instrumentation system at Pilgrim.
9.0 NRC MANAGEMENT MEETINGS AND OTIIER ACTIVITIES (30702) 9.1 Routine Meetings At periodic intervals during this inspection, meetings were held with senior plant management to discuss licensee activities and areas of concern to the inspectors. At the conclusion of the reporting period, the resident inspector staff conducted an exit n eeting _on January 7,1993 with licensee management, summarizing inspection activity and preliminary findings for this report period. No proprietary information was identified as being included in the report.
9.2 Other NRC Activities During the weeks of November 30 - December 4,1992 and December 14-18,1992 z Probabilistic Risk Assessment team inspection was conducted. Inspection results will be documented in NRC Inspection Report 50-293/92-81.