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| | issue date = 10/11/1979 | | | issue date = 10/11/1979 |
| | title = Submits Util Commitment to Agreements Reached at 790709 Meeting W/Nrc Re Activities Related to IE Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts. | | | title = Submits Util Commitment to Agreements Reached at 790709 Meeting W/Nrc Re Activities Related to IE Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts. |
| | author name = LIBRIZZI F P | | | author name = Librizzi F |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = SCHWENCER A | | | addressee name = Schwencer A |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000272 | | | docket = 05000272 |
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| {{#Wiki_filter:,-* | | {{#Wiki_filter:PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 October 11, .1979 Mr. Albert Schwencer, Chief Operating Reactors Branch #1 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
| Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 Mr. Albert Schwencer, Chief Operating Reactors Branch #1 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 | |
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| ==Dear Mr. Schwencer:== | | ==Dear Mr. Schwencer:== |
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| NRC IE BULLETIN NO. 79-07 SUPPLEMENTAL RESPONSE NO. 1 UNIT SALEM GENERATING STATION DOCKET NO. 50-272 October 11, .1979 On October 9, 1979, a meeting was held between representatives of our Company and Mr. Darrell G. Eisenhut and other NRC staff to discuss the activities related to IE Bulletin 79-07 nedessary to return Salem Unit No. 1 to service. The purpose of this letter is to document and commit to the agreements reached at that meeting. The program to bring us into complete compliance with IE Bulletin 79-07 will entail three phases as described below: Phase I Prior to entering Modes 3 and 4, the following work will be plished: 1) Completion of pipe stress analysis on safety related systems required for safe shutdown. | | NRC IE BULLETIN NO. 79-07 SUPPLEMENTAL RESPONSE NO. 1 UNIT SALEM GENERATING STATION DOCKET NO. 50-272 On October 9, 1979, a meeting was held between representatives of our Company and Mr. Darrell G. Eisenhut and other NRC staff to discuss the activities related to IE Bulletin 79-07 nedessary to return Salem Unit No. 1 to service. The purpose of this letter is to document and commit to the agreements reached at that meeting. |
| : 2) Re-evaluation of the associated supports, nozzles, and penetrations, within the inaccessible area. 3) Re-evaluation of the supports, nozzles, and penetrations for entire Auxiliary Feedwater System. 4) Re-evaluation of the supports for the Reactor Coolant System Pressure Boundry. 5) 190:l*lfJi'8 Field modification to supports and penetrations evaluated in (2), (3) & (4) that fail to meet our criteria stated in our September 21, 1979 submittal (Attachment I). Field modification to nozzles which fail to meet manufacturer's acceptance criteria. SEll\lCE 7910160 '-f ';iJ Q 95-2001 (200M) 2-78 f | | The program to bring us into complete compliance with IE Bulletin 79-07 will entail three phases as described below: |
| * A. Schwencer 10-11-79 IE Bulletin 79-07 6) Re-evaluation of the supports, nozzles, and tions of the following systems: a) High pressure safety injection using the chemical and Volume Control System. b) Low pressure safety injection using the Safety Injection System.
| | Phase I Prior to entering Modes 3 and 4, the following work will be accom-plished: |
| * c) Main Steam System up to the isolation valves to include the steam supply to the steam driven auxiliary feed pump. d) Containment Spray and Recirculation. | | : 1) Completion of pipe stress analysis on safety related systems required for safe shutdown. |
| : 7) Field modification to supports and penetrations evaluated in (6) that fail to have a factor of safety of at least 2. Field modification to nozzles which fail to meet manufacturer's ance criteria. | | : 2) Re-evaluation of the associated supports, nozzles, and penetrations, within the inaccessible area. |
| Phase I -Base*s For Entering Mode:s 3 And 4 Accomplishing items 1 through 6 and the corresponding' reanalysis and required by iE 79-02 the integrity of the reactor coolant system and the .availability of a short term heat sink (the auxiliary feedwater system). Accomplishing item 7 will give reasonable assurance of the operability of those systems. The quirements of the Technical Specifications will be at all times. As further justification, the reactor coolant activity as on October 9, 1979 is: Co-58 l.7lxlo-3uci/ml; Co-60 4.77xl0 uCi/ml; Mn-54 l.3lxlo-4uci/ml; and no detectable iodine. The source range counts are between 1 and 2 CPS. Given this very low overall activity level, any risks from radiological considerations during Mode 3 oper-ation are considered | | : 3) Re-evaluation of the supports, nozzles, and penetrations for entire Auxiliary Feedwater System. |
| | : 4) Re-evaluation of the supports for the Reactor Coolant System Pressure Boundry. |
| | : 5) Field modification to supports and penetrations evaluated in (2), (3) & (4) that fail to meet our criteria stated in our September 21, 1979 submittal |
| | ~\~ |
| | (Attachment I). Field modification to nozzles which 190:l*lfJi'8 fail to meet manufacturer's acceptance criteria. |
| | ~ SEll\lCE 7910160 |
| | '-f ';iJ |
| | '**\~ |
| | Q 95-2001 (200M) 2-78 |
| | |
| | f A. Schwencer |
| | * 10-11-79 IE Bulletin 79-07 |
| | : 6) Re-evaluation of the supports, nozzles, and penetra-tions of the following systems: |
| | a) High pressure safety injection using the chemical and Volume Control System. |
| | b) Low pressure safety injection using the Safety Injection System. |
| | * c) Main Steam System up to the isolation valves to include the steam supply to the steam driven auxiliary feed pump. |
| | d) Containment Spray and Recirculation. |
| | : 7) Field modification to supports and penetrations evaluated in (6) that fail to have a factor of safety of at least 2. Field modification to nozzles which fail to meet manufacturer's accept-ance criteria. |
| | Phase I - Base*s For Entering Mode:s 3 And 4 Accomplishing items 1 through 6 and the corresponding' reanalysis and modificatio~s required by iE Bull~tin 79-02 assure~ the integrity of the reactor coolant system and the .availability of a short term heat sink (the auxiliary feedwater system). Accomplishing item 7 will give reasonable assurance of the operability of those systems. The re~ |
| | quirements of the Technical Specifications will be me~ at all times. |
| | As further justification, the reactor coolant activity as a~~lyzed on October 9, 1979 is: Co-58 l.7lxlo-3uci/ml; Co-60 4.77xl0 uCi/ml; Mn-54 l.3lxlo-4uci/ml; and no detectable iodine. The source range counts are between 1 and 2 CPS. Given this very low overall activity level, any risks from radiological considerations during Mode 3 oper-ation are considered minimal~ |
| * Based on the above discussion, entering Modes 3 and 4 represents no threat to the health and safety of the public. | | * Based on the above discussion, entering Modes 3 and 4 represents no threat to the health and safety of the public. |
| * A. Schwencer 10-11-79 IE Bulletin 79-07 Phase II Prior to entering Modes 1 and 2 the following work will be plished: Field modification and corresponding modifications associated with the IE Bulletin to supports and penetrations evaluated in item 6 of Phase I that fail to meet our criteria as stated in our September 21, 1979 submittal (Attachment I). Modifications will be made within the time constraints of the action statements of the Technical Specifications if re-evaluation shows that system operability is affected.
| | |
| Phase II -Ba:ses For Entering Modes *1 and 2 Accomplishing all items in Phases I and II assures systems operability in compliance with the Technical Specifications and the ability to perform safe shutdown and maintain hot standby. Given these tions, entering Modes 1 and 2 represents no threat to the health and safety of the public during the period of time necessary to complete all of the requirements of IE Bulletin 79-07. In addition to the above safety bases justifying the return to service of the unit, PSE&G presently has an excessive amount of forced outage capacity. | | A. Schwencer |
| Added to our average short term forced outage of 1000 mw, we now have two large efficient units totaling 900 mw.which will not return to service until December 15, 1979 and March 1, 1980, tively. With Salem Unit 1 out of service, the economic penalty to the electric customers is approximately | | * 10-11-79 IE Bulletin 79-07 Phase II Prior to entering Modes 1 and 2 the following work will be accom-plished: |
| $600,000 per day. Additionally, the nuclear generation produced by Salem would save over 1.5 million . gallons of oil daily. Phase TII Within 60 days of entering Mode 2, .re-evaluation and field modifications as appropriate, of supports, nozzles, and penetrations remaining to be evaluated in accbrdance with IE .Bulletin 79-07 and 79-02; will be complished. | | Field modification and corresponding modifications associated with the IE Bulletin 79~02 to supports and penetrations evaluated in item 6 of Phase I that fail to meet our criteria as stated in our September 21, 1979 submittal (Attachment I). Modifications will be made within the time constraints of the action statements of the Technical Specifications if re-evaluation shows that system operability is affected. |
| Modifications will be made within the time constraints of the action statements of the Technical Specifications if re-evaluation shows system operability is affected. | | Phase II - Ba:ses For Entering Modes *1 and 2 Accomplishing all items in Phases I and II assures systems operability in compliance with the Technical Specifications and the ability to perform safe shutdown and maintain hot standby. Given these condi-tions, entering Modes 1 and 2 represents no threat to the health and safety of the public during the period of time necessary to complete all of the requirements of IE Bulletin 79-07. |
| * . -* A. Schwencer 10-11-79 IE Bulletin 79-07 The program and commitments described above are meant to modify the progra:i:n proposed by supplementary response letter to IE Bulletin 79-07 on September 21, 1979. In addition, this information should be sidered as a supplemental response to the letter of August 28, 1979 (Ref: IAL No. 79-12). . The completion of Phase I is presently scheduled for October 15, 1979, at which time it is our desire to proceed to Mode 3 to perform rod position indication calibrations and rod drop tests. This activity is expected to take approximately eight (8) days during which time the commitments of Phase II will be accomplished.
| | In addition to the above safety bases justifying the return to service of the unit, PSE&G presently has an excessive amount of forced outage capacity. Added to our average short term forced outage of 1000 mw, we now have two large efficient units totaling 900 mw.which will not return to service until December 15, 1979 and March 1, 1980, respec-tively. With Salem Unit 1 out of service, the economic penalty to the electric customers is approximately $600,000 per day. Additionally, the nuclear generation produced by Salem would save over 1.5 million |
| On October 23, 1979, the unit is expected to be ready to proceed into Mode 2 and 1. We believe this to be a realistic schedule and which can only be met by the mum effort of our plant staff and supporting groups and the cooperative effort of the NRC staff in Bethesda and Region I Inspection and forcement. | | . gallons of oil daily. |
| we sincerely appreciate the attention you and yqur staff are giving this subject. | | Phase TII Within 60 days of entering Mode 2, .re-evaluation and field modifications as appropriate, of supports, nozzles, and penetrations remaining to be evaluated in accbrdance with IE .Bulletin 79-07 and 79-02; will be ac-complished. Modifications will be made within the time constraints of the action statements of the Technical Specifications if re-evaluation shows th~t system operability is affected. |
| * Very truly yours, Frank P. Librizzi General | | |
| -Electric Production}}
| | A. Schwencer |
| | * 10-11-79 IE Bulletin 79-07 The program and commitments described above are meant to modify the progra:i:n proposed by supplementary response letter to IE Bulletin 79-07 on September 21, 1979. In addition, this information should be con-sidered as a supplemental response to the letter of August 28, 1979 (Ref: IAL No. 79-12). . |
| | The completion of Phase I is presently scheduled for October 15, 1979, at which time it is our desire to proceed to Mode 3 to perform rod position indication calibrations and rod drop tests. This activity is expected to take approximately eight (8) days during which time the commitments of Phase II will be accomplished. On October 23, 1979, the unit is expected to be ready to proceed into Mode 2 and 1. We believe this to be a realistic schedule and which can only be met by the maxi-mum effort of our plant staff and supporting groups and the cooperative effort of the NRC staff in Bethesda and Region I Inspection and En-forcement. we sincerely appreciate the attention you and yqur staff are giving this subject. |
| | * Very truly yours, Frank P. Librizzi General Manage~ - |
| | Electric Production}} |
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Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours)
ML18107A3641999-06-0404 June 1999
Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1
ML18107A3561999-06-0303 June 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments
ML18107A3611999-05-27027 May 1999
Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05
ML18107A3301999-05-24024 May 1999
Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves
ML18107A3291999-05-20020 May 1999
Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6)
ML18107A3031999-05-18018 May 1999
Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments
ML18107A2891999-05-13013 May 1999
Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness
ML18107A2951999-05-12012 May 1999
Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO
ML18107A2861999-05-11011 May 1999
Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE
ML18107A2481999-04-29029 April 1999
Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998
ML18107A2511999-04-27027 April 1999
Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses
ML18107A2371999-04-26026 April 1999
Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal
ML18107A2631999-04-26026 April 1999
Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements
ML18107A2411999-04-22022 April 1999
Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics
ML18107A1841999-04-14014 April 1999
Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl
ML18107A1981999-04-12012 April 1999
Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202
ML18107A1691999-04-12012 April 1999
Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld
ML20205K4541999-04-0808 April 1999
Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept
ML18106B1491999-04-0505 April 1999
Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined
ML20205F8981999-03-31031 March 1999
Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1)
ML18106B1431999-03-31031 March 1999
Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75
ML18107A2201999-03-30030 March 1999
Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARML18095A4881990-09-17017 September 1990
Requests Regional Waiver of Compliance from Tech Spec 3.6.2.3, Containment Cooling Sys. Waiver Requested in Order to Allow Replacement of Containment Fan Cooler Unit Motor #22 W/O Requiring Plant Shutdown
ML18095A4901990-09-13013 September 1990
Provides Supplemental Info Applicable to Clarification of 10CFR50,App R Exemption Request Re Fire Suppression Sys for Panel 335,per NRC Request
ML20059E6821990-09-0404 September 1990
Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld
ML18095A4641990-08-31031 August 1990
Forwards Revised Response to NRC Bulletin 88-004 Re Potential pump-to-pump Interaction.Util Pursuing Permanent Solution to Issue & Will Implement Appropriate Permanent Field Change by End of Unit 1 10th Refueling Outage
ML18095A4621990-08-31031 August 1990
Provides Revised Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Only HXs Exhibiting Unsatisfactory Test Results Will Be Inspected & Possibly Cleaned
ML18095A4431990-08-30030 August 1990
Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Rev 6 to Odcm.
ML18095A4531990-08-30030 August 1990
Forwards RERR-28, Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revised Odcm.W/O Revised ODCM
ML18095A4391990-08-29029 August 1990
Forwards Semiannual Rept Re fitness-for-duty Performance Data for 6-month Period Ending 900630,per 10CFR26.71(d).Rept Includes Testing Results,Random Testing Program Results & Confirmed Positive Tests for Specific Substances
ML18095A4421990-08-28028 August 1990
Clarifies 900710 Request for Amends to Licenses DPR-70 & DPR-75,changing Sections I & M.Under Proposed Change,Section I Should Be Changed to Read Section 2.J for License DPR-70 & Section M Changed to Read Section 2.N for License DPR-75
ML20059B6611990-08-22022 August 1990
Confirms That 10 Anchor/Darling Model S350W Swing Check Valves Installed at Plant,Per NRC Bulletin 89-002.All 18 Valves Inspected & Retaining Block Studs Replaced W/Upgraded Matl.No Crack Noted on Any Studs Which Were Replaced
ML20059C2861990-08-21021 August 1990
Provides Correction to 900810 Response to Request for Addl Info Re Util Request for Restatement of OL Expiration Dates
ML18095A4151990-08-10010 August 1990
Forwards Response to Request for Addl Info Re Reinstatement of OL Expiration Dates Based on Original Issuance of Ols. Advises That Correct Expiration Date for OL Proposed to Be 200418
ML18095A4091990-08-0909 August 1990
Forwards Responses to NRC Comments Re Plant Simulator Certification for 10CFR55.45(b)(2),per 891228 Ltr
ML18095A4061990-08-0808 August 1990
Forwards Corrected marked-up Pages for Tech Spec Table 3.3-11 Re Subcooling Margin Monitor & Reactor Vessel Level Instrumentation Sys,Per 900223 Ltr.Administrative Changes Made as Indicated
ML18095A3861990-07-30030 July 1990
Forwards Listing of Station Blackout Major Audit Items Resolution Scope,Per Station Blackout Schedule Commitment
ML18095A3661990-07-26026 July 1990
Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations
ML18095A3761990-07-26026 July 1990
Forwards Decommissioning Repts & Certification of Financial Assurance for Plants
ML18095A3721990-07-24024 July 1990
Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75
ML18095A3751990-07-18018 July 1990
Provides Status of Commitments Made to NRC by Util in 900109 Ltr Re NUREG-0737,Item II.D.1,per 900628 Telcon
ML18095A3741990-07-18018 July 1990
Provides Supplemental Info Re Facility sub-cooling Margin Monitor
ML18095A3611990-07-18018 July 1990
Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount.
ML18095A3621990-07-18018 July 1990
Forwards Corrected Tech Spec Page 3/4 3-5 for License Change Request 89-12 Submitted on 891227 & 900521
ML18095A3591990-07-13013 July 1990
Corrects Typo in 900702 Response to Generic Ltr 90-04 Re Schedule for Completion of Remaining Open Items
ML18095A3471990-07-11011 July 1990
Responds to NRC 900611 Ltr Re Violations Noted in Insp Repts 50-272/90-14 & 50-311/90-14.Corrective Actions:Directive from Radiation Protection Mgt to All Radiation Protection Personnel Issued Re Control of Compliance Agreement Sheets
ML18095A3451990-07-10010 July 1990
Forwards Addl Info Re License Change Request 89-03 Re Reactor Trip Sys Instrumentation
ML18095A3461990-07-10010 July 1990
Responds to NRC 900608 Ltr Re Violations Noted in Insp Repts 50-272/90-12 & 50-311/90-12.Corrective Actions:Assessment of ECCS & Component Performance Undertaken & ECCS Flow Testing Procedure Upgraded to Address Human Factors
ML18095A3491990-07-10010 July 1990
Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002
ML18095A3481990-07-10010 July 1990
Submits Supplemental Rept Identifying Root Cause of Missed Commitment & Corrective Actions to Assure Future Compliance Re Implementation of Mods to Facility PASS
ML18095A3441990-07-0909 July 1990
Provides Written Notification Re Change in Calculated Peak Clad Temp,Per 900606 Verbal Notification
ML18095A3281990-07-0202 July 1990
Responds to NRC 900530 Ltr Re Violations Noted in Insp Repts 50-272/90-09 & 50-311/90-09.Corrective Actions:Util Intends to Use Nuclear Shift Supervisor as Procedure Reader & EOP, Rev 2 Under Development
ML18095A3301990-07-0202 July 1990
Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues.Table Describing Status of Generic Safety Issue Implementation Encl
ML18095A3391990-06-29029 June 1990
Forwards Correction to 890913 License Change Request 88-09, Consisting of Tech Spec Page 3/4 4-13
ML18095A3221990-06-28028 June 1990
Provides Supplemental Info Re 900223 Proposed Revs to Tech Specs for Reactor Vessel Level Instrumentation Sys.Tables 3.3-11a & 3.3-11b Should Be Combined Into Single Table
ML18095A3231990-06-28028 June 1990
Responds to NRC 900518 Ltr Re Violations Noted in Insp Repts 50-272/90-10,50-311/90-10 & 50-354/90-07.Two Noncited Violations Disputed.Util fitness-for-duty Program Exceeds Part 26 Requirements for Positive Blood Alcohol Limits
ML18095A3241990-06-28028 June 1990
Forwards Retyped Pages to 871224 License Change Request 87-15 & Modified,Per 900620 Ltr
ML18095A3211990-06-26026 June 1990
Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout
ML18095A3161990-06-25025 June 1990
Forwards Supplemental Info Re Response to Generic Ltr 88-14. All Committed Actions Complete as of 900613
ML18095A3141990-06-25025 June 1990
Provides Schedule Change for Implementation of Control Room Mods.Schedule Modified to Address Overhead Annunciator Human Engineering Discrepancies During Phase III
ML18095A3201990-06-25025 June 1990
Responds to NRC 900524 Ltr Re Violations Noted in Insp Repts 50-272/90-11 & 50-311/90-11.Corrective Actions:All Overdue Operations & Maint Procedure Files Reviewed for Outstanding Rev Requests & Procedure Upgrade Program Initiated
ML18095A3001990-06-20020 June 1990
Provides Addl Info Re Application for Amend to Licenses DPR-70 & DPR-75 Concerning Turbine Valve Surveillance Interval,Per 900320 Request.Util Adding Direction to Personnel If Unnacceptable Flaws Found
ML20043H6221990-06-20020 June 1990
Provides Supplemental Info Re NRC Bulletin 88-008 for Fifth Refueling Outage.Detailed Test Rept Being Prepared to Document Results of Each Individual Insp Re Insulation, Hangers & High Energy Break Areas
ML18095A2991990-06-20020 June 1990
Forwards Westinghouse Affidavit Supporting 900412 Request for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790
ML18095A2721990-06-0808 June 1990
Responds to NRC 900329 Ltr Re Weaknesses Noted in Insp Repts 50-272/90-80 & 50-311/90-80.Corrective Actions:Fire Doors Placed on Blanket Preventive Maint Work Order & Damaged Fire Doors Will Be Repaired Immediately
ML18095A2711990-06-0606 June 1990
Submits Info in Support of 900522 Verbal Request for Relief from Requirements of ASME Section XI
ML18095A2611990-06-0101 June 1990
Forwards Corrected Operating Data Rept, Page for Apr 1990 Monthly Operating Rept
ML18095A2521990-06-0101 June 1990
Forwards Application in Support of Request for Renewal of NJPDES Permit NJ0005622,per Requirements of Subsection 3.2 of Plant Environ Protection Plan,Nonradiological
ML18095A2591990-06-0101 June 1990
Forwards Corrected Unit Shutdown & Power Reductions, Page for Apr 1990 Monthly Operating Rept
ML18095A2411990-05-30030 May 1990
Submits Special Rept 90-4 Addressing Steam Generator Tube Plugged During Fifth Refueling Outage.Plugging Completed on 900516.Cause of Tube Degradation Attributed to Normal Wear Due to Erosion/Corrosion Factors
ML18095A2431990-05-30030 May 1990
Informs of Util Plans Re Facility Cycle 6 Reload Core, Expected to Achieve Burnup of 16600 Mwd/Mtu.All Postulated Events within Allowable Limits Based on Review of Basis of Cycle 6 Reload Analysis & Westinghouse SER
ML18095A2531990-05-29029 May 1990
Provides Addl Info Re End of Life Moderator Temp Coefficient.Feedback Used in Steam Line Break Has No Relationship to Full Power Moderator Density Coefficient
1990-09-04
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Text
PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 October 11, .1979 Mr. Albert Schwencer, Chief Operating Reactors Branch #1 U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Schwencer:
NRC IE BULLETIN NO. 79-07 SUPPLEMENTAL RESPONSE NO. 1 UNIT SALEM GENERATING STATION DOCKET NO. 50-272 On October 9, 1979, a meeting was held between representatives of our Company and Mr. Darrell G. Eisenhut and other NRC staff to discuss the activities related to IE Bulletin 79-07 nedessary to return Salem Unit No. 1 to service. The purpose of this letter is to document and commit to the agreements reached at that meeting.
The program to bring us into complete compliance with IE Bulletin 79-07 will entail three phases as described below:
Phase I Prior to entering Modes 3 and 4, the following work will be accom-plished:
- 1) Completion of pipe stress analysis on safety related systems required for safe shutdown.
- 2) Re-evaluation of the associated supports, nozzles, and penetrations, within the inaccessible area.
- 3) Re-evaluation of the supports, nozzles, and penetrations for entire Auxiliary Feedwater System.
- 4) Re-evaluation of the supports for the Reactor Coolant System Pressure Boundry.
- 5) Field modification to supports and penetrations evaluated in (2), (3) & (4) that fail to meet our criteria stated in our September 21, 1979 submittal
~\~
(Attachment I). Field modification to nozzles which 190:l*lfJi'8 fail to meet manufacturer's acceptance criteria.
~ SEll\lCE 7910160
'-f ';iJ
'**\~
Q 95-2001 (200M) 2-78
f A. Schwencer
- 6) Re-evaluation of the supports, nozzles, and penetra-tions of the following systems:
a) High pressure safety injection using the chemical and Volume Control System.
b) Low pressure safety injection using the Safety Injection System.
- c) Main Steam System up to the isolation valves to include the steam supply to the steam driven auxiliary feed pump.
d) Containment Spray and Recirculation.
- 7) Field modification to supports and penetrations evaluated in (6) that fail to have a factor of safety of at least 2. Field modification to nozzles which fail to meet manufacturer's accept-ance criteria.
Phase I - Base*s For Entering Mode:s 3 And 4 Accomplishing items 1 through 6 and the corresponding' reanalysis and modificatio~s required by iE Bull~tin 79-02 assure~ the integrity of the reactor coolant system and the .availability of a short term heat sink (the auxiliary feedwater system). Accomplishing item 7 will give reasonable assurance of the operability of those systems. The re~
quirements of the Technical Specifications will be me~ at all times.
As further justification, the reactor coolant activity as a~~lyzed on October 9, 1979 is: Co-58 l.7lxlo-3uci/ml; Co-60 4.77xl0 uCi/ml; Mn-54 l.3lxlo-4uci/ml; and no detectable iodine. The source range counts are between 1 and 2 CPS. Given this very low overall activity level, any risks from radiological considerations during Mode 3 oper-ation are considered minimal~
- Based on the above discussion, entering Modes 3 and 4 represents no threat to the health and safety of the public.
A. Schwencer
- 10-11-79 IE Bulletin 79-07 Phase II Prior to entering Modes 1 and 2 the following work will be accom-plished:
Field modification and corresponding modifications associated with the IE Bulletin 79~02 to supports and penetrations evaluated in item 6 of Phase I that fail to meet our criteria as stated in our September 21, 1979 submittal (Attachment I). Modifications will be made within the time constraints of the action statements of the Technical Specifications if re-evaluation shows that system operability is affected.
Phase II - Ba:ses For Entering Modes *1 and 2 Accomplishing all items in Phases I and II assures systems operability in compliance with the Technical Specifications and the ability to perform safe shutdown and maintain hot standby. Given these condi-tions, entering Modes 1 and 2 represents no threat to the health and safety of the public during the period of time necessary to complete all of the requirements of IE Bulletin 79-07.
In addition to the above safety bases justifying the return to service of the unit, PSE&G presently has an excessive amount of forced outage capacity. Added to our average short term forced outage of 1000 mw, we now have two large efficient units totaling 900 mw.which will not return to service until December 15, 1979 and March 1, 1980, respec-tively. With Salem Unit 1 out of service, the economic penalty to the electric customers is approximately $600,000 per day. Additionally, the nuclear generation produced by Salem would save over 1.5 million
. gallons of oil daily.
Phase TII Within 60 days of entering Mode 2, .re-evaluation and field modifications as appropriate, of supports, nozzles, and penetrations remaining to be evaluated in accbrdance with IE .Bulletin 79-07 and 79-02; will be ac-complished. Modifications will be made within the time constraints of the action statements of the Technical Specifications if re-evaluation shows th~t system operability is affected.
A. Schwencer
- 10-11-79 IE Bulletin 79-07 The program and commitments described above are meant to modify the progra:i:n proposed by supplementary response letter to IE Bulletin 79-07 on September 21, 1979. In addition, this information should be con-sidered as a supplemental response to the letter of August 28, 1979 (Ref: IAL No. 79-12). .
The completion of Phase I is presently scheduled for October 15, 1979, at which time it is our desire to proceed to Mode 3 to perform rod position indication calibrations and rod drop tests. This activity is expected to take approximately eight (8) days during which time the commitments of Phase II will be accomplished. On October 23, 1979, the unit is expected to be ready to proceed into Mode 2 and 1. We believe this to be a realistic schedule and which can only be met by the maxi-mum effort of our plant staff and supporting groups and the cooperative effort of the NRC staff in Bethesda and Region I Inspection and En-forcement. we sincerely appreciate the attention you and yqur staff are giving this subject.
- Very truly yours, Frank P. Librizzi General Manage~ -
Electric Production
