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| {{#Wiki_filter:Public Service Electric and Gas Company | | {{#Wiki_filter:Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations V;irch 3, 19f.9 W. T. Russell, Ad~inistrator. |
| * Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President
| | NRC Region I 475 Allendale Rd. |
| -Nuclear Operations W. T. Russell, NRC Region I 475 Allendale Rd. King of Prussia, PA 19406 Gentlemen: | | King of Prussia, PA 19406 Gentlemen: |
| V;irch 3, 19f.9 REQUEST FOR DISCRETIONARY ENFORCEMENT TECHNICAL SPECIFICATION 3.6.2.1 SALEM GENERATING STATION FACILITY OPERATING LICENSE NO. DPR-75 UNIT NO. 2 DOCKET NO. 50-311 Public Service Electric and Gas Company (PSE&G) hereby requests discretionary enforcement with regard to the Action Statement for the Limiting Condition for Operation (LCO) 3.6.2.1, Containment Spray System, of the Salem Generating Station Unit No. 2 Technical Specifications.
| | REQUEST FOR DISCRETIONARY ENFORCEMENT TECHNICAL SPECIFICATION 3.6.2.1 SALEM GENERATING STATION FACILITY OPERATING LICENSE NO. DPR-75 UNIT NO. 2 DOCKET NO. 50-311 Public Service Electric and Gas Company (PSE&G) hereby requests discretionary enforcement with regard to the Action Statement for the Limiting Condition for Operation (LCO) 3.6.2.1, Containment Spray System, of the Salem Generating Station Unit No. 2 Technical Specifications. As discussed in Attachment 1, plant operation subsequent to the granting of this relief request would not create a significant hazard to public health and safety and is justified on technical and economic bases. The requested relief would provide an additional "4-day period beyond the expiration of the current action statement allowance in which to restore the affected Containment Spray System train to an operable condition. |
| As discussed in Attachment 1, plant operation subsequent to the granting of this relief request would not create a significant hazard to public health and safety and is justified on technical and economic bases. The requested relief would provide an additional "4-day period beyond the expiration of the current action statement allowance in which to restore the affected Containment Spray System train to an operable condition. | | This request has.become necessary due to the existence of through-wall pinhole leaks on a section of piping on the discharge side of the 21 Containment Spray Pump, rendering the associated containment spray train inoperable. |
| This request has.become necessary due to the existence of wall pinhole leaks on a section of piping on the discharge side of the 21 Containment Spray Pump, rendering the associated containment spray train inoperable. | | Within 14 days of our compliance with the requirements of the subject specification, PSE&G will submit a special report identifying all corrective*actions taken. |
| Within 14 days of our compliance with the requirements of the subject specification, PSE&G will submit a special report identifying all corrective*actions taken. 8903140310 PDR ADOCK p PDC 2 Your timely assistance is requested, via a verbal approval of this request by 6:00 a.m., Monday, March 6, 1989, in order to avert an unnecessary plant shutdown as detailed herein. If you have questions, we will be pleased to discuss them with you. Enclosures C Mr. J. C. Stone Sincerely Stanley LaBruna Vice President | | 8903140310 OQO~O~ |
| -Nuclear Operation Licensing Project Manager -Salem Ms. K. Halvey Gibson Senior Resident Inspector
| | PDR ADOCK 5§656~11 p PDC |
| -Salem Ms. J. Moon, Interim Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, N.J. 08625 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 STATE OF NEW JERSEY COUNTY OF SALEM SS. Ref* REQUEST FOR DISCRETIONARY ENFORCEMENT | | |
| -SGS, UNIT 2 Stanley LaBruna, being duly sworn according to law deposes and says: I am Vice President | | 2 Your timely assistance is requested, via a verbal approval of this request by 6:00 a.m., Monday, March 6, 1989, in order to avert an unnecessary plant shutdown as detailed herein. If you have questions, we will be pleased to discuss them with you. |
| -Nuclear Operations of Public Service Electric arid Gas Company, and as such, I find the matters set forth in our letter dated March 3, 1989, concerning Facility Operating License DPR-75 for Salem Generating Station, Unit No. 2, true to the best of my knowledge, information and belief. 7 Subscribed and Sworn to before me this 3rd day of (Y/Cl/Ycfv , 19 8 9 My Commission expires on | | Sincerely Stanley LaBruna Vice President - |
| : *'*' ... | | Nuclear Operation Enclosures C Mr. J. C. Stone Licensing Project Manager - Salem Ms. K. Halvey Gibson Senior Resident Inspector - Salem Ms. J. Moon, Interim Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, N.J. 08625 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
| 'i:-; : . , : ... : | | |
| TTr"ACHMENT 1 TECHNICAL 3.6.2. CONTAINMENT SPRAY SYSTEM Tee hnical Speci fie a tion Limiting Condi ti on for Operation (JJCO) 3.6.2.1. identifies the operability requirements for the Salem Unit 2 Containment Spray System. The containment Spray System consists of two independent spray systems with each system capable of taking suction from the RWST and transferring suction to the RHR pump discharge for the purpose of containment depressurization and cooling capability in the event of a LOCA. The containment Spray System also provides a mechanism for removing iodine from the containment atmosphere via a common spray additive tank which inputs sodium hydroxide to the spray system via an eductor. The Action Statement for LCO 3.6.2.1 indicates that one train of the Containment Spray System may be out of service for a period of 72 hours. | | Ref* REQUEST FOR DISCRETIONARY ENFORCEMENT - SGS, UNIT 2 STATE OF NEW JERSEY SS. |
| | COUNTY OF SALEM Stanley LaBruna, being duly sworn according to law deposes and says: |
| | I am Vice President - Nuclear Operations of Public Service Electric arid Gas Company, and as such, I find the matters set forth in our letter dated March 3, 1989, concerning Facility Operating License DPR-75 for Salem Generating Station, Unit No. 2, true to the best of my knowledge, information and belief. |
| | ~7 7 Subscribed and Sworn to before me this 3rd day of (Y/Cl/Ycfv , 19 8 9 |
| | ~-\L **:~ : *'*' ... *-=- |
| | My Commission expires on NOTARY;--'.:;~, 'i:-; : . |
| | , :... :*.~ |
| | |
| | TTr"ACHMENT 1 TECHNICAL SPECIFICAT~ON 3.6.2. CONTAINMENT SPRAY SYSTEM Tee hnical Speci fie a tion Limiting Condi ti on for Operation (JJCO) 3.6.2.1. identifies the operability requirements for the Salem Unit 2 Containment Spray System. The containment Spray System consists of two independent spray systems with each system capable of taking suction from the RWST and transferring suction to the RHR pump discharge for the purpose of containment depressurization and cooling capability in the event of a LOCA. The containment Spray System also provides a mechanism for removing iodine from the containment atmosphere via a common spray additive tank which inputs sodium hydroxide to the spray system via an eductor. |
| | The Action Statement for LCO 3.6.2.1 indicates that one train of the Containment Spray System may be out of service for a period of 72 hours. |
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| ==SUMMARY== | | ==SUMMARY== |
| of CURRENT SITUATION At 6:00 a.m. on Friday, March 3, 1989, during the performance of a valve surveillance in the mechancial penetration area, a series of pinhole leaks were noted on a portion of piping on the discharge side of the 21 Containment Spray Pump. Further investigation revealed the leaks to be coming from a formed portion of 8" pipe between check valves 21CS4 and 21CS48 on the discharge side of the pump. The formed section of pipe appeared to be discolored around 1 Statement deadline of 6:00 a.m., Monday March 6, 1989 requiring a plant shutdown from 100% of rated power. PSE&G therefore requests that NRC Region I grant discretionary enforcement of the Action Statement for LCO 3.6.2.1 of the Salem Unit 2 Technical Specifications for a period that would allow an additional 4 days, beyond the presently allowed 72 hours, to complete the restoration of the 21 Containment Spray train to operable status by replacement of the affected piping. PSE&G believes that this extension of time will not place the plant in an unsafe condition since the availability of the other containment spray train and the containment fan coil units meet plant design considerations regarding containment pressure reduction and iodine removal in the event of a LOCA. This is discussed in detail in the technical justification presented below. PSE&G belives that this occurrence represents a situation which was beyond our control and could not have been foreseen since the piping run is not part of the ISI program and justifies this request for discretionary enforcement. | | of CURRENT SITUATION At 6:00 a.m. on Friday, March 3, 1989, during the performance of a valve surveillance in the mechancial penetration area, a series of pinhole leaks were noted on a portion of piping on the discharge side of the 21 Containment Spray Pump. Further investigation revealed the leaks to be coming from a formed portion of 8" pipe between check valves 21CS4 and 21CS48 on the discharge side of the pump. The formed section of pipe appeared to be discolored around 1 |
| Operation under the requested discretionary enforcement will not place the plant in an unsafe condition. | | |
| PSE&G belives that there is ample technical justification for the requested relief, as described in the following paragraphs. | | Statement deadline of 6:00 a.m., Monday March 6, 1989 requiring a plant shutdown from 100% of rated power. PSE&G therefore requests that NRC Region I grant discretionary enforcement of the Action Statement for LCO 3.6.2.1 of the Salem Unit 2 Technical Specifications for a period that would allow an additional 4 days, beyond the presently allowed 72 hours, to complete the restoration of the 21 Containment Spray train to operable status by replacement of the affected piping. |
| 3 the area where the pinhole leaks had occurred. | | PSE&G believes that this extension of time will not place the plant in an unsafe condition since the availability of the other containment spray train and the containment fan coil units meet plant design considerations regarding containment pressure reduction and iodine removal in the event of a LOCA. This is discussed in detail in the technical justification presented below. |
| Visual and ultrasonic examination was subsequently performed in an attempt to determine the failure mechanism. | | PSE&G belives that this occurrence represents a situation which was beyond our control and could not have been foreseen since the piping run is not part of the ISI program and justifies this request for discretionary enforcement. |
| As a result of the NDE performed, PSE&G believes that the portion of piping was sensitized due to the forming operation, making it susceptible to pitting attack. The existence of stagnant borated water may also have contributed to the corrosion mechanism. | | Operation under the requested discretionary enforcement will not place the plant in an unsafe condition. PSE&G belives that there is ample technical justification for the requested relief, as described in the following paragraphs. |
| PSE&G has performed a walkdown on the analogous portions of piping on the discharge of the 22 Contaiment Spray Pump. This walkdown revealed that there was no dicoloration of the piping and that the piping run was considerably straighter than that on which the pinhole leaks were encountered. | | 3 |
| PSE&G has planned-an ultrasonic examination of the like portion of the 22 contaiment spray train piping to ensure that similar deterioration has not occurred. | | |
| PSE&G will also walkdown the like portions of piping of the Salem Unit 1 Containment Spray System for any similarity. | | the area where the pinhole leaks had occurred. |
| The need for NDE on the Unit 1 piping will be evaluated based on the results of the walkdowns. | | Visual and ultrasonic examination was subsequently performed in an attempt to determine the failure mechanism. As a result of the NDE performed, PSE&G believes that the portion of piping was sensitized due to the forming operation, making it susceptible to pitting attack. The existence of stagnant borated water may also have contributed to the corrosion mechanism. |
| Salem Generating Station plant management is concerned that repair efforts on the affected portion of the 22 Containment Spray System Piping will extend beyond the current 72 hours LCO 3.6.2.1 Action 2 | | PSE&G has performed a walkdown on the analogous portions of piping on the discharge of the 22 Contaiment Spray Pump. This walkdown revealed that there was no dicoloration of the piping and that the piping run was considerably straighter than that on which the pinhole leaks were encountered. PSE&G has planned-an ultrasonic examination of the like portion of the 22 contaiment spray train piping to ensure that similar deterioration has not occurred. |
| | PSE&G will also walkdown the like portions of piping of the Salem Unit 1 Containment Spray System for any similarity. The need for NDE on the Unit 1 piping will be evaluated based on the results of the walkdowns. |
| | Salem Generating Station plant management is concerned that repair efforts on the affected portion of the 22 Containment Spray System Piping will extend beyond the current 72 hours LCO 3.6.2.1 Action 2 |
| | |
| | ~~stification that the request will not create a significant hazard to publ~c he~lth & safety. |
| | Extension of the allowed outage time for one train of containment spray has been evaluated for impact to the public health and safety. The following paragraphs address identified concerns. |
| | The failure mechanism has been tentatively identified to be internal pitting caused by a combination of sensitization of the piping due to the spool piece forming process coupled with stagnant borated water trapped in the piping during testing due to a dowmsteam check valve. The alternate train does not have similar bends and thus were not formed in the same manner and were not sensitized. This is confirmed by the presence of heat discoloration on the leaking pipe which is not present on the opposite train~ No sign of leakage was observed during visual inspection of the opposite train. Walkdowns were performed on both units piping in the area affected by the pitting. No indication of leaking was observed. Additional NDE is being performed on Unit 2 to confirm that the failure mechanism is 4 |
| | |
| | limited to a small section of piping. Any indications to the contrary will cause reevaluation of our plans. Based on the preliminary indications, the affected area is limited and not indicative of a widespread failure mechanism. |
| | A Probabilistic Risk Analysis (PRA) has been performed to determine the affect of extending the allowed outage time from 3 to 7 days on the increase in the probability of a core melt. The analysis assumed one train out of service for 7 days, the alternate train subject only to random failure and 3 containment fan coil units available. The results of this analysis indicate that the increase in the probability of core melt is approximately 2xl0 -8 /yr or approximately 1/100 of 1% of the total core melt probability. This is considered to be insignificant increase in the core melt probability and will not significantly affect public health and safety. |
| | The basis of the Technical Specification for availability of the core spray system is two fold. First it is a portion of th~ |
| | equipment necessary for control of contaiment pressure. The UFSAR basis for pressure control requires any combination listed below: |
| | : 1. Two containment spray systems, or |
| | : 2. One containment spray and three containment fan coil unit, or |
| | : 3. Five containment fan coil units 5 |
| | |
| | Technical Specifications require 5 fan coil units to be operable. |
| | Currently the 5 fan coil units are operable. Therefore with the remaining containment spray system operable, the containment pressure control requirement is satisfied. |
| | The second function of the spray system is iodine removal from the containment steam atmosphere duing a LOCA. The UFSAR states that this function is satisfied with one spray system operable. In the extremely unlikely event of a LOCA during this 7-day period, coupled with failure of the second spray system, the impact to thyroid doses to the public has been evaluated. The UFSAR indicates that a partition factor of 100 is applied due to the effect of the spray system. Thyroid doses at the site boundary assuming the spray system is operable is .028 rem. If the partition factor is not applied, a 100 fold increase results. |
| | This yields a thyroid dose of 2.8 rem. The 10CFR 100 dose limit to the thyoid is 300 rem. Therefore the dose increase does not represent a significant risk to the health and safety of the public. |
| | Additionally there is industry precedent for extension of the action statement from 72 hours to 7 days. The Byrom and Braidwood stations has received License Amendments allowing permanent extension of the action statement to 7 days. This amendment was issued January 21, 1988. |
| | 6 |
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| |
|
| that the request will not create a significant hazard to
| | Based on the above reasons it is concluded that extending the action statement from 72 hours to 7 days for outage of one containment spray system will not cause a significant hazard to the public health and safety. |
| & safety. Extension of the allowed outage time for one train of containment spray has been evaluated for impact to the public health and safety. The following paragraphs address identified concerns.
| | 7}} |
| The failure mechanism has been tentatively identified to be internal pitting caused by a combination of sensitization of the piping due to the spool piece forming process coupled with stagnant borated water trapped in the piping during testing due to a dowmsteam check valve. The alternate train does not have similar bends and thus were not formed in the same manner and were not sensitized.
| |
| This is confirmed by the presence of heat discoloration on the leaking pipe which is not present on the opposite No sign of leakage was observed during visual inspection of the opposite train. Walkdowns were performed on both units piping in the area affected by the pitting. No indication of leaking was observed.
| |
| Additional NDE is being performed on Unit 2 to confirm that the failure mechanism is 4 limited to a small section of piping. Any indications to the contrary will cause reevaluation of our plans. Based on the preliminary indications, the affected area is limited and not indicative of a widespread failure mechanism.
| |
| A Probabilistic Risk Analysis (PRA) has been performed to determine the affect of extending the allowed outage time from 3 to 7 days on the increase in the probability of a core melt. The analysis assumed one train out of service for 7 days, the alternate train subject only to random failure and 3 containment fan coil units available.
| |
| The results of this analysis indicate that the increase in the probability of core melt is approximately
| |
| -8 2xl0 /yr or approximately 1/100 of 1% of the total core melt probability.
| |
| This is considered to be insignificant increase in the core melt probability and will not significantly affect public health and safety. The basis of the Technical Specification for availability of the core spray system is two fold. First it is a portion of equipment necessary for control of contaiment pressure.
| |
| The UFSAR basis for pressure control requires any combination listed below: 1. Two containment spray systems, or 2. One containment spray and three containment fan coil unit, or 3. Five containment fan coil units 5 Technical Specifications require 5 fan coil units to be operable.
| |
| Currently the 5 fan coil units are operable.
| |
| Therefore with the remaining containment spray system operable, the containment pressure control requirement is satisfied.
| |
| The second function of the spray system is iodine removal from the containment steam atmosphere duing a LOCA. The UFSAR states that this function is satisfied with one spray system operable.
| |
| In the extremely unlikely event of a LOCA during this 7-day period, coupled with failure of the second spray system, the impact to thyroid doses to the public has been evaluated.
| |
| The UFSAR indicates that a partition factor of 100 is applied due to the effect of the spray system. Thyroid doses at the site boundary assuming the spray system is operable is .028 rem. If the partition factor is not applied, a 100 fold increase results. This yields a thyroid dose of 2.8 rem. The lOCFR 100 dose limit to the thyoid is 300 rem. Therefore the dose increase does not represent a significant risk to the health and safety of the public. Additionally there is industry precedent for extension of the action statement from 72 hours to 7 days. The Byrom and Braidwood stations has received License Amendments allowing permanent extension of the action statement to 7 days. This amendment was issued January 21, 1988. 6
| |
| * Based on the above reasons it is concluded that extending the action statement from 72 hours to 7 days for outage of one containment spray system will not cause a significant hazard to the public health and safety. 7}}
| |
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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 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 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 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 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
[Table view] |
Text
Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations V;irch 3, 19f.9 W. T. Russell, Ad~inistrator.
NRC Region I 475 Allendale Rd.
King of Prussia, PA 19406 Gentlemen:
REQUEST FOR DISCRETIONARY ENFORCEMENT TECHNICAL SPECIFICATION 3.6.2.1 SALEM GENERATING STATION FACILITY OPERATING LICENSE NO. DPR-75 UNIT NO. 2 DOCKET NO. 50-311 Public Service Electric and Gas Company (PSE&G) hereby requests discretionary enforcement with regard to the Action Statement for the Limiting Condition for Operation (LCO) 3.6.2.1, Containment Spray System, of the Salem Generating Station Unit No. 2 Technical Specifications. As discussed in Attachment 1, plant operation subsequent to the granting of this relief request would not create a significant hazard to public health and safety and is justified on technical and economic bases. The requested relief would provide an additional "4-day period beyond the expiration of the current action statement allowance in which to restore the affected Containment Spray System train to an operable condition.
This request has.become necessary due to the existence of through-wall pinhole leaks on a section of piping on the discharge side of the 21 Containment Spray Pump, rendering the associated containment spray train inoperable.
Within 14 days of our compliance with the requirements of the subject specification, PSE&G will submit a special report identifying all corrective*actions taken.
8903140310 OQO~O~
PDR ADOCK 5§656~11 p PDC
2 Your timely assistance is requested, via a verbal approval of this request by 6:00 a.m., Monday, March 6, 1989, in order to avert an unnecessary plant shutdown as detailed herein. If you have questions, we will be pleased to discuss them with you.
Sincerely Stanley LaBruna Vice President -
Nuclear Operation Enclosures C Mr. J. C. Stone Licensing Project Manager - Salem Ms. K. Halvey Gibson Senior Resident Inspector - Salem Ms. J. Moon, Interim Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, N.J. 08625 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Ref* REQUEST FOR DISCRETIONARY ENFORCEMENT - SGS, UNIT 2 STATE OF NEW JERSEY SS.
COUNTY OF SALEM Stanley LaBruna, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service Electric arid Gas Company, and as such, I find the matters set forth in our letter dated March 3, 1989, concerning Facility Operating License DPR-75 for Salem Generating Station, Unit No. 2, true to the best of my knowledge, information and belief.
~7 7 Subscribed and Sworn to before me this 3rd day of (Y/Cl/Ycfv , 19 8 9
~-\L **:~ : *'*' ... *-=-
My Commission expires on NOTARY;--'.:;~, 'i:-; : .
, :... :*.~
TTr"ACHMENT 1 TECHNICAL SPECIFICAT~ON 3.6.2. CONTAINMENT SPRAY SYSTEM Tee hnical Speci fie a tion Limiting Condi ti on for Operation (JJCO) 3.6.2.1. identifies the operability requirements for the Salem Unit 2 Containment Spray System. The containment Spray System consists of two independent spray systems with each system capable of taking suction from the RWST and transferring suction to the RHR pump discharge for the purpose of containment depressurization and cooling capability in the event of a LOCA. The containment Spray System also provides a mechanism for removing iodine from the containment atmosphere via a common spray additive tank which inputs sodium hydroxide to the spray system via an eductor.
The Action Statement for LCO 3.6.2.1 indicates that one train of the Containment Spray System may be out of service for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
SUMMARY
of CURRENT SITUATION At 6:00 a.m. on Friday, March 3, 1989, during the performance of a valve surveillance in the mechancial penetration area, a series of pinhole leaks were noted on a portion of piping on the discharge side of the 21 Containment Spray Pump. Further investigation revealed the leaks to be coming from a formed portion of 8" pipe between check valves 21CS4 and 21CS48 on the discharge side of the pump. The formed section of pipe appeared to be discolored around 1
Statement deadline of 6:00 a.m., Monday March 6, 1989 requiring a plant shutdown from 100% of rated power. PSE&G therefore requests that NRC Region I grant discretionary enforcement of the Action Statement for LCO 3.6.2.1 of the Salem Unit 2 Technical Specifications for a period that would allow an additional 4 days, beyond the presently allowed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, to complete the restoration of the 21 Containment Spray train to operable status by replacement of the affected piping.
PSE&G believes that this extension of time will not place the plant in an unsafe condition since the availability of the other containment spray train and the containment fan coil units meet plant design considerations regarding containment pressure reduction and iodine removal in the event of a LOCA. This is discussed in detail in the technical justification presented below.
PSE&G belives that this occurrence represents a situation which was beyond our control and could not have been foreseen since the piping run is not part of the ISI program and justifies this request for discretionary enforcement.
Operation under the requested discretionary enforcement will not place the plant in an unsafe condition. PSE&G belives that there is ample technical justification for the requested relief, as described in the following paragraphs.
3
the area where the pinhole leaks had occurred.
Visual and ultrasonic examination was subsequently performed in an attempt to determine the failure mechanism. As a result of the NDE performed, PSE&G believes that the portion of piping was sensitized due to the forming operation, making it susceptible to pitting attack. The existence of stagnant borated water may also have contributed to the corrosion mechanism.
PSE&G has performed a walkdown on the analogous portions of piping on the discharge of the 22 Contaiment Spray Pump. This walkdown revealed that there was no dicoloration of the piping and that the piping run was considerably straighter than that on which the pinhole leaks were encountered. PSE&G has planned-an ultrasonic examination of the like portion of the 22 contaiment spray train piping to ensure that similar deterioration has not occurred.
PSE&G will also walkdown the like portions of piping of the Salem Unit 1 Containment Spray System for any similarity. The need for NDE on the Unit 1 piping will be evaluated based on the results of the walkdowns.
Salem Generating Station plant management is concerned that repair efforts on the affected portion of the 22 Containment Spray System Piping will extend beyond the current 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO 3.6.2.1 Action 2
~~stification that the request will not create a significant hazard to publ~c he~lth & safety.
Extension of the allowed outage time for one train of containment spray has been evaluated for impact to the public health and safety. The following paragraphs address identified concerns.
The failure mechanism has been tentatively identified to be internal pitting caused by a combination of sensitization of the piping due to the spool piece forming process coupled with stagnant borated water trapped in the piping during testing due to a dowmsteam check valve. The alternate train does not have similar bends and thus were not formed in the same manner and were not sensitized. This is confirmed by the presence of heat discoloration on the leaking pipe which is not present on the opposite train~ No sign of leakage was observed during visual inspection of the opposite train. Walkdowns were performed on both units piping in the area affected by the pitting. No indication of leaking was observed. Additional NDE is being performed on Unit 2 to confirm that the failure mechanism is 4
limited to a small section of piping. Any indications to the contrary will cause reevaluation of our plans. Based on the preliminary indications, the affected area is limited and not indicative of a widespread failure mechanism.
A Probabilistic Risk Analysis (PRA) has been performed to determine the affect of extending the allowed outage time from 3 to 7 days on the increase in the probability of a core melt. The analysis assumed one train out of service for 7 days, the alternate train subject only to random failure and 3 containment fan coil units available. The results of this analysis indicate that the increase in the probability of core melt is approximately 2xl0 -8 /yr or approximately 1/100 of 1% of the total core melt probability. This is considered to be insignificant increase in the core melt probability and will not significantly affect public health and safety.
The basis of the Technical Specification for availability of the core spray system is two fold. First it is a portion of th~
equipment necessary for control of contaiment pressure. The UFSAR basis for pressure control requires any combination listed below:
- 1. Two containment spray systems, or
- 2. One containment spray and three containment fan coil unit, or
- 3. Five containment fan coil units 5
Technical Specifications require 5 fan coil units to be operable.
Currently the 5 fan coil units are operable. Therefore with the remaining containment spray system operable, the containment pressure control requirement is satisfied.
The second function of the spray system is iodine removal from the containment steam atmosphere duing a LOCA. The UFSAR states that this function is satisfied with one spray system operable. In the extremely unlikely event of a LOCA during this 7-day period, coupled with failure of the second spray system, the impact to thyroid doses to the public has been evaluated. The UFSAR indicates that a partition factor of 100 is applied due to the effect of the spray system. Thyroid doses at the site boundary assuming the spray system is operable is .028 rem. If the partition factor is not applied, a 100 fold increase results.
This yields a thyroid dose of 2.8 rem. The 10CFR 100 dose limit to the thyoid is 300 rem. Therefore the dose increase does not represent a significant risk to the health and safety of the public.
Additionally there is industry precedent for extension of the action statement from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days. The Byrom and Braidwood stations has received License Amendments allowing permanent extension of the action statement to 7 days. This amendment was issued January 21, 1988.
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Based on the above reasons it is concluded that extending the action statement from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days for outage of one containment spray system will not cause a significant hazard to the public health and safety.
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