Similar Documents at Salem |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML18107A5601999-10-18018 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 IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection 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 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 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. 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 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 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 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 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 ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection 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 ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection 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 ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 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 ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 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 ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection 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 ML18107A3371999-05-21021 May 1999 Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622 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 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 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 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 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 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] |
See also: IR 05000272/1986023
Text
' . * Corbin A. McNeill, Jr. Public Service Electric and Gas Company Public Service Electric and Ga? Company P 0. Box236. Hancocks Bridge. i\JJ 08038 609 339-4;300
V:ce Pres*cen:
- February 13, 1987 NLR-N87017
United States Nuclear Regulatory
Commission
Document Control Desk Washington, DC 20555 Attention:
Mr. Robert F. Heishman, Chief Vendor Programs Branch Division of Quality Assurance
Gentlemen:
Vendor and Technical
Training Center Programs Off ice of Inspection
and Enforcement
NRC INSPECTION
50-272/86-23
AND 50-311/86-23
REVISED RESPONSE TO INSPECTION
REPORT SALEM
STATION DOCKET NOS. 50-272 AND 50-311 meeting was held on
3, 1987 at NRC Region I to discuss our responses
to those Salem EQ inspection
findings subject to the 10CFR50.49
enforcement
criteria delineated
in Generic Letter 86-15. During the meeting, NRC staff representatives
were notified of changes to our previous responses (dated November 7, 1986 and December 15, 1986) to the subject inspection
report. Those changes are being formally submitted
by this letter and its attachment.
We first request that our previous response to Potential
Enforcement/Unresolved
Item 50-272/86-23-03:
50-311/86-23-03
regarding
the qualification
of Rockbestos
EPR and Coaxial cahle be withdrawn.
An in-depth review of our November 7_, 1986 response to this finding was performed
by PSE&G prior to the meeting at NRC Region I. The results of the review determined
that although PSE&G EQ personnel
were knowledgeable
of the additional
tests which substantiated
the results of the questionable
Rockbestos
test reports noted in IE Information
Notice 84-44, these test reports had not been formally analyzed and referenced
in the Rockbestos
EQ file. As such, the inspection
finding in this area is not disputed.
The review of the response to Potential
Enforcement/Unresolved
Item 50-272/86-23-04:
50-311/86-21-04
also uncovered
certain *discrepancies
in the information
presented
with regard to the Limitorque
gear case grease reliefs. Correction
of these
Q * . ' * * Document Control Desk 2 2/13/87 discrepancies
does not alter our position that tha grease reliefs were not required for the operability
of the Limitorque
operators
in containment
under Salem plant-specific
post-accident
conditions.
The statement
in Attachment
B-2 to the November 7, 1986 letter with regard to the reasons for the clogging of the drains in FIRL Test Report F-C3441 were misinterpreted
in that the drains were clogged with grease which had come out of the grease relief valve after the flooding of the test chamber. The grease actually came out of the relief valve prior to the flooding of the chamber. The grease used was not identified.
This misinterpretation
does not alter the overall analysis performed
on the subject item and has been corrected
in the "Revised Attachment
B-2." The grease referred to in the November 7, 1986 submittal, Mobil Grease 28, is used in the intermittent
gear box (not the main gear box) and is valid for that application.
The intermittent
gear box has no grease relief valve. The grease used in the main gear box is EXXON Nebula EPO or EPl. Although it is not a synthetic
lubricant
like Mobil
28, it has been evaluated
and the results indicate that it would perform in a manner similar to that presented
for Mobil Grease 28. Analysis of the in-containment
post-accident
conditions
with respect to the warming of the gear box and the subsequent
expansion
of the grease have indicated
that appreciable
expansion
would not occur and that the
compartment
would not be breached.
Also, the statement
in the November 7, 1986 submittal
with regard to "appreciable
expansion" of the grease only occurring
afier reaching the dropping point should not have been interpreted
to mean that no expansion
occurs until the dropping point is reached. It is understood
that expansion
will begin to occur upon the initial warming of the grease. To avoid any confusion, this statement
has been withdrawn.
A Revised Attachment
B-2 is provided with this letter. Please contact Mr. Bruce Preston at 609-339-5129
with any questions
you may have* Your cooperation
in this matter is appreciated.
Sincerely, Attachment
Document Control Desk C Mr. D. C. Fischer Licensing
Project Manager Mr. T. J. Kenny Senior Resident Inspector
Dr. T. E. Murley Regional Administrator
Region I 3 2/13/87 -I
Revised Attachment B -2 A potential
enforcement
item was identified
by the NRC related to the absence of gear box grease reliefs on Limitorque
actuators
located in containment.
The
is that the gear box grease reliefs must be provided in the plant installation
since they were installed
in the Limitorque
actuators
subjected
to the LOCA/MSLB
test simulation.
It is verbally stated by Limitorque
that the relief valve provides for relief of grease and the pressure build-up which occurs due to thermal expansion
at prolonged
elevated temperatures.
However, Limitorque
also states in Report
pages 14 and 15, that "Limitorque
actuators
for Nuclear Plant applications
are designed to operate in normal and accident conditions
without depending
on absolute sealing. In fact, the ambient is not absolutely
restricted
from entering the actuator.
The seals, are of no importance
for qualification
and, therefore, require no consideration
for the qualification".
Mr. J. Drab of Limitorque
stated in a telephone
conversation
with Ms. B. Horst of PSE&G on April 9, 1986, as documented
in the Record of Verbal Discossions, "They are not an EQ
and their absence does not adversely
affect the qualification
status of Limitorques", Mr. Drab and Limitorque
have subsequently
refused to issue this statement
in a signed letter. In FIRL test report F-C3441 prepared for Limitorque (used in their BWR Containment
Report-60376A), it was identified
that flooding of the test chamber occurred from a build up of steam condensate
when the test chamber condensate
trap became clogged. This was attributed
to a grease build up in the trap caused by grease that had evidently
come out of the relief valve during the test. The test was stopped during the fifth day. Prior to the test discontinuation, the specimen had been subjected
to 2, three hour transients
at +340°F, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at +320°F and 4 1/2 days at +250°F. The Salem plant temperature
profile for a Main Steamline
Break (MSLB) shows a peak temperature
of 347°F for 72 seconds, droppinq to approximately
260°F in less than 5 minutes. For a LOCA, a peak temperature
of 268°F is reached and maintained
for 12 1/2 minutes. Within 30 minutes the temperature
will fall below 250°F. Each of these accidents
produces a peak pressure of 43.2 psig for 170 minutes. Therefore, an external positive pressure is maintained
for the duration of the temperature
transient
minimizing
the pressure differential
due to possible internal pressure buildup. da8/l
'< ' .. The Superheat
Temperature
Test Report #B0027 was performed
to determine
the internal temperatures
of components
in the Limitorque
valve actuators
due to superheat
ambient temperatures.
It illustrates
that exposure of the actuator to high environmental
temperatures
for short durations
of time will not raise internal unit temperatures
to an equal state. It was demonstrated
by analysis that an*ambient
temperature
of 492°F in excess of 17 minutes would only result in a maximum internal temperature
of 315°F for the electrical
switch compartment
components
and motor windings.
Actual testing indicates
that an ambient temperature
of 385°F was reached at 186 minutes and at this time the temperature
inside the motor was only 282°F. It can therefore
be concluded
that the effects of high ambient temperatures
over a short time period will not result in excessively
high internal temperatures.
As such, excessive
internal pressure will not result. The grease utilized for lubrication
of the intermittent
gear box in the Limitorques
at Salem is Mobil Grease 28. This. is a synthetic
lubricant
exhibiting
high pressure characteristics
at temperatures
in excess of 350°F. This grease has a dropping point of approximately
500°F, which precludes
its changing to a liquid state even under superheat
conditions.
The main gearbox utilizies
a calcium complex base grease manufactured
by Exxon and known as Nebula EPl (or EPO). This grease can be used for applications
up to 400°F, it contains an Extreme Pressure (EP) additive to help increase the film strength of the oil, and has a dropping
of approximately
500°F. The EPl grease exhibits similar characteristics
to the Mobil 28 grease and both types of grease are approved by Limitorque
for in-containment
applications
in the operators.
In Test Report B0003, an actuator containing
Nebula EPl gearbox grease was exposed to a sustained
temperature
of 250°F for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Grease relief valves were not installed
on this actuator as Limitorque
evidently
determined
that exposure to 250°F and 25 psig during an accident test was not sufficient
to justify their usage ** The test unit actuator was a SMB-0 type, which is rather small, containing
approximately
9.5 pounds of gearbox grease. Larger actuat9rs
contain up to 75 pounds of grease (SMB-4 or 5 type). Given the small size of the test unit, it can be deduced that maintaining
the temperature
at 250°F for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will bring .the entire unit to therma1 equilibrium, including
the gearbox grease. It can therefore
be determined
that EPl type grease can be heated to 250°F and will not expand to any degree that would require the use of a grease relief on the actuator.
da8/2
... * By utilizing
the Salem accident profile for temperature
and pressure for worst case Main Steam Line Break (MSLB) and Loss-of -Coolant Accident (LOCA), it can be determined
by analysis that exposure to either condition
inside containment
will not cause the gearbox grease to exceed 250°F. This is due to the fact that the maximum LOCA temperature
of 268°F is reached in approximately
4 minutes following
the start of the accident, after which the temperature
slowly begins to decrease.
Thirty minutes following
the start of the event the temperature
has fallen below 250°F. As is evident, the time duration is not sufficient
to heat the grease above 250°F. During the MSLB event, a maximum temperature
of 347°F is *reached in approximately
100 seconds. This temperature
is maintained
for 72 seconds, after which the temperature
rapidly begins to decrease.
Thirty minutes following
the start of the event the temperature
falls below 250°F. Again the time duration at the temperature
above 250° is not sufficient
to heat the grease above 250°F. The characteristics
of the grease would be a factor in determining
the necessity
of grease reliefs on the gear case housing. Since the greases utilized during the qualification
tests were not identified, a correlation
of actual parameters
cannot be made. However, a temperature
resistant
grease such as the Nebula EPl appears to have been used. As proven by test, the internal temperature
of the operator, even un-der superheated
ambient conditions, would not cause the internal temperature
to exceed saturated
conditions.
This temperature
is well within the design limits of the specified
grease and would not be cause for it to exhibit appreciable
expansion.
A pressure buildup sufficient
to breach tbe switch compartment
is not possible under the Salem Station postulated
accident conditions
and therefore
grease relief plugs are not required to maintain operability
of the valve. It should be noted that PSE&G's position was, and still is, that a determination
to not use grease reliefs was made from all known and available
information.
Based on the verbal information
from Limitorque, the Salem PWR specific accident profiles and knowledge
of the data in the test report; it was determined
that the grease relief valves were not necessary;
would not prevent the valves from performing
their safety function;
and their absence would not be in violation
of the qualification
status of the actuators.
da8/3
. For information
purposes, at the time of the inspection, there *were 7 in-containment
class lE actuators
in Salem Unit 1 that were identified
by Station QA personnel
as not having grease . relief valves. Salem Unit 2 had grease relief valves installed
on all in-containment
actuators.
In accordance
with the recommendation
to. utilize grease reliefs as good engineering
practice, grease reliefs are now installed
on all in-containment
actuators
at Salem. da8/4