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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10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses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:INCOMING CORRESPONDENCE
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 ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl 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) 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20195G3721999-06-0707 June 1999 Informs That Proposed Indicators Failed QA Assessments for Digital Verification,Validation & Control of Software. Proposed Mod Can Be Completed on-line ML20195B5021999-05-27027 May 1999 Provides Suppl Info to 990203 Request of Beco That NRC Consent to Indirect Transfer of Control of Util Interest in License DPR-35.Request Described Proposed Merger of Bec Energy with Commonwealth Energy Sys ML20207D4681999-05-24024 May 1999 Provides Addl Info to That Included in Beco Ltr 98-123 Dtd 981001,addressing NRC Concerns Described in GL 96-06, Concerning Waterhammer in Reactor Bldg Closed Cooling Water Sys ML20195B9051999-05-20020 May 1999 Forwards Completed Renewal Applications for Listed Operators.Without Encls ML20206J4901999-05-0606 May 1999 Forwards Completed License Renewal Application,Including Forms NRC-398 & 396 for Sc Power,License OP-6328-3 ML20206P0711999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, for K Walz,License SOP-10886-1.Encl Withheld IAW 10CFR2.790(a)(6) ML20206D3621999-04-27027 April 1999 Informs NRC That Final Five Sys self-assessments Required to Fulfill Commitment Made in 980828 Response to Insp Rept 50-293/98-04 Were Completed on 990422.Completion Was Delayed by High Priority Refueling Outage 12 Preparatory Work ML20205R9871999-04-21021 April 1999 Forwards Affidavit of JW Yelverton of Entergy Nuclear Generation Co Supporting Request for Withholding Info from Rept on Audit of Financial Statements for Year Ended 971231. Pages 16 & 18 of Subj Rept Also Encl ML20207B0891999-04-20020 April 1999 Forwards e-mail Message from Constituent,J Riell Re Y2K Compliance of Nuclear Power Plant in Plymouth,Massachusetts. Copy of Article Entitled Nuke Plants May Not Be Y2K Ready Also Encl ML20206A2741999-04-16016 April 1999 Dockets Encl Ltr Which Was Sent to AL Vietti-Cook Re Condition of Approval of Transfer of License & License Condition for DPR-35.Encl Resolves Issues Between Attorney General of Commonwealth of Massachusetts & Applicants ML20205P9131999-04-16016 April 1999 Submits Applicant Consent to Listed Condition of Approval of Transfer of License & License Condition for License DPR-35 & Affirmatively Request That NRC Adopt Listed Language in Order ML20205P9271999-04-16016 April 1999 Withdraws Motion for Leave to Intervene & Petition for Summary Or,In Alternative,For Hearing.Requests That NRC Adopt Condition of Approval of Transfer of License & License Condition Agreed to Beco & Entergy Nuclear Generation Co ML20205Q9231999-04-15015 April 1999 Forwards Proprietary & non-proprietary Addl Info in Support of Request to Transfer of Plant FOL & Matls License to Entergy Nuclear Generation Co.Proprietary Info Withheld,Per 10CFR2.790 ML20205P9631999-04-15015 April 1999 Provides Attachments a & B in Support of Request for Transfer of Plant Operating License & NRC Matl License from Beco to Entergy Nuclear Generation Co as Submitted in Ref 1. Info Provided in Response to Request at 990413 Meeting ML20205H9281999-04-0707 April 1999 Requests Withdrawal of Uwua Locals 369 & 387 Unions Joint Intervention in Listed Matter ML20205F3731999-04-0202 April 1999 Submits Addl Info Provided in Support of Request for Transfer of Pilgrim Nuclear Power Station Operating License & Matls License.State of Ma Order Authorizing Divestiture & Copy of Financial Arrangement Encl ML20204H3771999-03-26026 March 1999 Informs That Local 387,Utility Workers Union of America,AFL- Cio Voted to Approve New Contract with Entergy Nuclear Generation Co & Voted to Accept Boston Edison Divestiture Agreement ML20205D4231999-03-24024 March 1999 Forwards Decommissioning Funding Rept for Pilgrim Nuclear Power Station,In Accordance with 10CFR50.75(f)(1) 1999-09-09
[Table view] |
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10CFR50.54(f)
. BOSTON EDISON Pilgum Nuclear Power Station ,
Rocky Hill Road l Plymouth, Massachusetts o2360 i
George W. Davis october 25, 1991 sena v.ce prescent - Nuclur BECo 91- 147 U.S. Nuclear Regulatory Commission l Document Control-Desk l Hashington, DC 20555 l License DPR-35 Docket 50-293 l Response to Generic Letter 91-06, Resolution of Generic l
Issue A-30. "Adeauacy of Safety-Related DC Power Supplies" l
This letter responds to NRC questions asked in Generic Letter (GL) 91-06.
Attachment I contains a list of the GL 91-06 questions with our responses.
If you have any further questions regarding this response, please contact our ,
Licensing staff. j
^
/ /
',/ , )'{P % w
' G. H. Davis BRS/cic/6291 Attachm nt cc: (See page 2) l l Commonwealth of Massachusetts)
County of Plymouth )
i Then personally appeared before me, George H. Davis, who being duly sworn, did state that he is Senior Vice President - Nuclear of Boston Edison Company and that he is duly authorized to execute and file the submittal contained herein in the name and on behalf of Boston Edison Company and that the statements in said submittal are true to the best of his knowledge and beller.
My commission expires: Oc 84,z f # f - 7'M ! ~
DATE NOTARf PUBLIC
\
- \
i 9111050191 011025 rh i PDR ADOCK 05000293 l
l
/ -
t ,- P PDR {\
BOSTON EDISON COMPANY O. S. Nuclear Regulatory Connission Page 2 cc: Mr. R. Eaton, Project Manager Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Mail Stop: 1401 U. S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockvilla, MD 20852 U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Senior NRC Resident Inspector Pilgrim Nuclear Power Station
ATTACHMENT 1
- l. Unit Pilarim Nuclear Power Station
- 2. a. The number of independent redundant divisions of Class lE or safety-related dc power for this plant is two . (Include any separate Class IE or safety-related dc, such as any dc dedicated to the diesel generators.)
- b. The number of functional safety-related divisions of de power necessary to attain safe shutdown for this unit is one .
- 3. Does the control room at this unit have the following separate, independentiy annunciated alarms and indications for each division of dc power?
- a. Alarms
- 1. Battery disconnect or circuit breaker open? No
- 2. Battery charger disconnect or circuit breaker open (both input at and output dc)? Yes and N_Q resoectivelv - See resconse to question 5
- 3. dc system ground? Yes
- 4. dc bus undervoltage? Yes
- 5. dc bus overvoltage? No
- 6. Battcry charger failure? No.
- 7. Battery discharge? No
- b. Indications
- 1. Battery float charge current? No
- 2. Battery circuit output current? No
- 3. Battery discharge? No (local)
- 4. Bus voltage? No (local)
- c. Does the unit have written procedures for response to the above alarms and indications? Yes - See resPDDie to agestion 5
- 4. Does this unit have indication of bypassed and inoperable statuslof circuit breakers or other devices that can be used to disconnect the battery and battery charger from its dc bus and the battery charger from its ac power source during maintenance or testing? No. See rejponse to aues tions 3.a.J_and 3.a ._1
_1_
. _ . - _. _ _ _ _ . . . ~ _ _ . _ _ . _ . _ _ _ _ _ . _ . _ _ _ _ . _ ,
1 E.; -j
- 5. If the answer to any part of question 3 or 4 is no, then provide information justifying the existing design features of the facility's safety-related dc systems.
Question 3.a.1 There are no alarms to indicate if the battery circuit breaker or the disconnect is open. Presently, the circuit breaker.is verified to be in the correct position three times a day during performance of the Nuclear Power Plant Tour procedure and the battery disconnect is key locked in the closed position. The battery breaker and disconnect are only opened during performance of maintenance. This activity is administratively controlled in accordance with approved maintenance procedures that require independent verification to ensure the system is restored to its proper alignment following maintenance. ,
l Based on our existing design features and the described l administrative procedural controls,_ correct breaker position is '
assured at all times.
J Question 3.a.2 The battery charger input ac supply is monitored and annunciated in ;
-the control room. -The alarm is a common alarm for the A and B chargers and monitors ac supply voltage and annunciates if supply voltage to the charger is lost.
The output breaker of the :harger is not directly monitored. There is, however,-an undervoltage alarm that monitors de bus-voltage and-will annunciate when the bus voltage decreases below the setpoint.
The setpoint-is conservatively set to annunciate before the battery voltage decreases below a level at which the safety objective of the
~ battery could not be met.
Also, the circuit breaker is verified to-be inlthe correct position three times a day during the performance of the Nuclear Power Plant
~ Tour procedure. The charger supply breaker to the de bus is only
- opened during. performance of maintenance. = This activity is administratively controlled in accordance with approved plant- '
procedures that-require independent verificationLto ensure the system-is. restored toLits proper alignment. . In addition, battery voltage is monitored'during the Nuclear Power Plant. tour. Any significant drop below normal float voltage would indicate = a problem-with the charger.
Based on our existing design: features and the administrative
. procedural: controls described above, correct alignment of the battery charger input and output'circult breakers are assured at all times.
F -If a-breaker were to open or the battery charger become disconnected this would be quickly detected and corrective action taken.
s
l 1
Question 3.a.5 The de bus voltage is monitored by the EPIC computer which provides an alarm on high or low voltage. This alarm is associated with the EPIC system and is logged on the alarm printout. On receipt, the alarm is validated oy checking the local voltage indicator at the battery bus. If the high voltage condition is confirmed corrective action would be taken in accordance with plant procedures.
Question 3.a.6 As discussed in response to Question 3.a.2 the battery charger initiates a common alarm for the A and B chargers when ac input power is lost. If the battery charger fails and output dc power is lost the batteries will begin to discharge. As the battery discharges and the voltage decreases the low voltage setpoint will cause an alarm in the control room. Alarm response procedures provide clear direction for corrective action to be taken. Additionally, the battery is equipped with an ammeter that monitors battery discharge. This ammeter reading is checked and logged three times a day during performance of the Nuclear Power Plant Tour procedure.
Based on our existing design features, the plant tour walkdown procedure verifying the batteries are not discharging, the loss of at input power alarm, and the undervoltage alarm on the dc bus, a battery charger failure would be detected and corrective action promptly initiated.
Question 3.a.7 Battery discharge is not directly monitored or alarmed in the Control Room. The battery bus is equipped with a local dual directional ammeter which is monitored and logged three times a day during the performance of the Nuclear Power Plant Tour procedure.
Also, the batterv is equipped with an undervoltage alarm. This alarm is set conservatively high and when tripped would be indicative of a discharging battery. In addition to the alarm the battery bus voltage is monitored three times a day. Any battery float voltage significantly lower than normal would also be indicative of a discharging battery.
These existing design features and plant tours assure the battery condition is being monitored to ensure it is properly charged.
Question 3.b.1 There is no indication in the Control Room for battery float charge current. There is a local dual directional ammeter which monitors battery current magnitude and direction. This ammeter is checked and logged three times a day during performance of the Nuciear Power Plant Tour. This ammeter is not sensitive enough to measure float charge current but would measure any large float current and/or a battery discharge current.
+
Question 3 b.2 There is an ammeter on the battery charger that provides indication of bus circuit output current plus battery float charge current which is usually very small during normal operation. This indication ,
provides information that is useful when determining if the charger is operating properly and the total load on the bus. During abnormal conditions when bus load is high the battery circuit output current can be obtained by summing the charger output and battery output currents.
Question 3.b.3 Battery discharge is indicated locally by the battery output ammeter that is monitored three times a day. Also, if the batteries were discharging the undervoltage alarm setpoint would soon be reached providing annunciation in the Control Room. The alarm response procedure provides clear direction for corrective action to be taken.
l Question 3.b.4 The battery voltage is indicated locally and is monitored and logged three times a day during performance of the Nuclear Power Plant Tour. If the battery voltage were significantly less than normal float voltage it would be indicative of a failed battery charger and corrective action would be taken. The dc bus undervoltage alarm provides backup to the Nuclear Power Plant tour surveillance.
Monitoring the dc bus voltage and the battery circuit ammeter provides assurance the battery is charged and the charger is operating properly.
Question 3.c There are specific written alarm response procedures for a dc system ground, battery charger failure (loss of ac power to charger), and dc bus undervoltage condition.
The battery output current and the dc bus voltage are monitored and logged. Also, as discussed in response to Questions 3.a.1 and 3.a.2 there are no alarms to indicate if the battery circuit breaker or the disconnect is open; however, the circuit breaker is verified to be in the correct position three times a day and the disconnect is key locked in the closed position. If these devices were found to be incorrectly positioned it would be brought to the attention of the Watch Engineer who would make an operability determination and initiate corrective action. Any anomalies would be evaluated in accordance with plant procedures. The dc bus overvoltage. condition, which is monitored and alarmed on the EPIC system, would be evaluated in a similar manner.
- 6. (1) Have you conducted a review of maintenance and testing activities to minimize the potential for human error causing more than one dc division to be unavailable? See resoonse_to auestion 9 and (2) Do plant procedures prohibit maintenance or testing on redundant dc divisions at the same time? Yes
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If the facility Technical Specifications have provisions equivalent to those found in the Westinghouse and Combustion Engineering Standard Technical Specifications for maintenance and surveillance, then question 7 may be skipped and a statement to that effect may be inserted here. __Eg1 acolicable
- 7. Are maintenance, surveillance and test procedures regarding station batteries conducted teutinely at this plant? Specifically:
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- a. At least once per 7 days are the following verified to be within acceptable limits:
- 1. Pilot cell electrolyte level? Yes
- 2. Specific gravity or charging current? Yes
- 3. Float voltage? Yes
- 4. Total bus voltage on float charge? Yes
- 5. Physical condition of all cells? No
- b. At least once per 92 days, or within 7 days after a battery discharg6, overcharge, or if the pilot cell readings are outside the 7-day surveillance requirements are the following verified to be within acceptable limits:
1 Electrolyte level of each cell? Yes - See resconse to_ question 9
- 2. The average specific gravity of all cells? _Yes - See response to auestion 9
- 3. The specific gravity of each cell? Yes - See rest.onse to gu stion 9
- 4. The average electrolyte temperature of a representative number of cells? Yes - See resoonig lo auestion 9
- 5. The float voltage of each cell? Yes - See resoonse to ayestion 9
- 6. Visually inspect or measure resistance of terminals and connectors (including the connectors at the dc bus)? Yes - Sea resconse to auestion 9
- c. At least every 18 months are the following verified:
- 1. Low resistance of each con .ction (by test)? Yes
- 2. Physical condition of the battery? Yes
- 3. Battery charger capability to deliver rated ampere output to the dc bus? Yes - See resoonse tq_ question 9
- 4. The capability of the battery to deliver its design duty cycle to the dc bus? Yes - See resoonse to auestion 9
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- 5. Each individual cell volisge is within acceptable limits during
. the 5ervice test? ligLApplinble. _$ec_rliponie__to_qutitipIL9
- d. At least every 60 months, is capacity of each battery verified by performance of a discharge test? leim41ei_10Ad_dischAL9L.ifilli per f ormed_ty.ery._11Lt9nthi.
- e. At least ennually, is the battery capetity serified by performance discharge test, if the battery shows signs of degradation or has reached 85% of the expected service life? _SsLte}conse to queltica 9
- 8. Does this plant have operational features such that following loss of one safety-related dc power supply or bus:
- a. Capability is taaintained for ensuring continued and adequate reactor cooling? _Yes
- b. Reactor coolant system integrity and isolation capability are riiaintained? Yes
- c. Operating procedures, instrumentation (tr-luding indicators and annunciators), and control functions are adequate to initiate systems as required to maintain adequate core cooling? Yes
- 9. If the answer to any part of questions 6, 7 or 8 is no, ther, stovide your basis for not performing the maintenance, surveillance and test procedures described and/or the bases for not including the operational features cited.
Question 6 Procedures Faye not been specifically reviewed to ensure maintenance and testing activities minisize the notential for human error ciusing more than one dc division f be unave lable. However, maintenar.e and testing on redundant de divisions at tM m e time is prohibited by our plant maintenance procedures. Since md atenance and testing on more than one dc division at a time is not allowed, the potential for concurrent human error affecting more than one dc division is inherently minimized.
Question 7.a.5 The phyd u l condition of all cells are verified during the monthly battery surveillance procedure. Additionally, during performance of the weekly and quarterly battery surveillances any degradation of the cells would be observed and corrective action taken.
Question 7.b The items specified in Question 7.b are verified once per 92 days and following a battery discharge test as part of our battery surveillances.
The batteries are not suojected to random over charging or discharging, however, if they were observed to be discharged or overcharged appropriate corrective action would be taken. Also, battery electrolyte level is
d monitorM three times a day during performance of the Nuclear Power Plant
. Tour. If the 7-day surveillance requirements for the pilot cell readings are outside the acceptance criteria corrective action is immediately taken by performing single cell charging during which the electrolyte level, specific gravity, electrolyte temperature, and cell voltage of the pilot )
l cell are monitored. l Question 7.b.6 i
The resistance of the battery terminals is measured (ductor test) on a i semi-annual basis in accordance with the PNPS preventive niaintennte schedule.
There is also a monthly battery surveillance procedure that specifically performs a visual inspection of the battery terininals as well as checking the battery racks, battery room ventilation, and general appearance of the battery rooms. The battery terminals are visually inspected for degradation during the performance of system walkdowns that are performed weekly. Maintenance personnel are trained to look for any signs of physical degradation and/or corrosion of battery terminals during performance of weekly and quarterly battery surveillances although not specifically required by procedure.
The connectors at the de bus are not inspected at this time as there have not been any failures associated with these connections. The battery terminal connections are considered more significant for inspection purposes due to historical evidence of corrosion. He will review the pctential need to incorporate the provisions to inspect the bus connections into our maintenance procedures.
Question 7.c.3 There is not a specific test presently performed that verifies the battery charger capability to deliver rsted arnpere output. However, following the 18 month battery discharge test the charger is required to recharge the batteries. The charger is operated at close to rated output thus functionally verifying the charger output capability. This test will be revised to include a verification of the charger's capability to deliver its rated output.
Questien 7.c.4.
The duty cycle of the battery h verified 'y using the manufacturer's duty cycle test in conjunction ide the battery load discharge test to prove the batteries have sufficient capacity to fulfill their safety function.
Question 7.c.5.
He do not perform a service test. PNPS Technical Specifications require i
the performing of a rated load discharge test once/ cycle. During this
! test cell voltage is monitored to be within acceptable limits.
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1 Question 7,e
. Present)y the batteries are at 80% of the expected service life. The .
batteries are being evaluated to determine an optimum replacement schedule j based on past battery surveillances and future expected loss of service :
life.
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