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 05000311/1997006
Text
' ,, __ . ** Public Service Electric and Gas Company Louis F. Storz Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700
Senior Vice President
-Nuclear Operations
United States Nuclear Regulatory
Commission
Document Control Desk Washington, DC 20555 SUPPLEMENTAL
RESPONSE TO A NOTICE OF VIOLATION
INSPECTION
REPORT 50-311/97-06
SALEM GENERATING
STATION UNIT NO. 2 DOCKET NO. 50-311 Gentlemen:
Inspection
Report No. 50-311/97-06
for Salem Nuclear Generating
Station Unit No. 2 was transmitted
to Public
Electric & Gas Company (PSE&G) on May 30, 1997. Within the scope of this report, one violation
of NRC requirements
was c.i ted. The violation
involved the failure to follow established
procedures
for the documentation
of test results. By letter dated June 30, 1997 (Our Ref: LR-N970371), PSE&G submitted
its response to the cited violation.
As stated in the original PSE&G response, the root cause of the violation (all f; cited examples)
was attributed
to poor human performance
of l)J personnel
performing
the activities
and poor human performance
by management
in the oversight
of these activities.
The corrective
actions stated in the June 30 response were designed to address ';* the root cause in its broadest form. To provide a complete understanding
of PSE&G's actions taken, PSE&G is supplementing
the June 30, 1997 original response to address the specific actions taken relative to each of the cited examples.
Mssrs. D. Powell and M. Rencheck of PSE&G discussed
the submittal
of this supplemental
response with Mr. W. Ruland (NRC Region I) via telephone
on July 9, 1997. 9707220344
970716 PDR ADOCK 05000311 G PDR *..* *,_, _ .. \J Printedon
\:I Recycled Paper 1111111111111111111111111111111111111111
- * Document Control Desk LR-N970449
2 JUL 16 1997 Additionally, by letter dated April 11, 1997 (Our Ref-: N97194), PSE&G responded
to a similar violation
transmitted
in Inspection
Report 50-311/96-21.
This violation
involved deficient
conditions
for the testing of the Control Room Area Air Conditioning
System. As a result of subsequent
PSE&G investigation, as well as NRC inspections, other deficient
conditions
were identified
relative to the same design modification
test procedures.
In light of the applicability
of these findings to Control Room Area Air Conditioning, and in response to Inspection
Report 50-311/97-06
request, PSE&G considers
the information
provided in the June 30, 1997 letter to be relevant to the April 11, 1997 response.
In the June 30, 1997 response, PSE&G stated that (Corrective
action E) ten non-HVAC system Special Test Procedures (STPs) in five systems were reviewed.
PSE&G would like to expand on this corrective
action by identifying
the procedures
reviewed.
The STPs reviewed are: Fire Protection
2EC-3298 Package 1 -STPs 1-3 lEC-3701 Package 1 -STP 1 Electrical
2EC-3332 Package 2 -STPs 1 & 2 Diesel lEC-3529 Package 2 -STP 1 Service Water 2EC-3590 Package 6 -STPs 1-3 2EC-3590 Package 11 -STP 1 2EC-3590 Package 6 -STPs 1-3 2EC-3590 Package 17 -STPs 1-7 2EC-3590 Package 18 -STPs 1-5 Safety Injection
2EC-3461 Package 1 -STPs 1 & 2 95-4933
- Document Control Desk LR-N970449
3 JUL 16 1997 Attachment
I to this letter contains the original violation
as cited in Inspection
Report 50-311/97-06.
Attachment
II contains PSE&G's supplemental
information
relative to these *events. Should there be any questions
regarding
this submittal, please contact us. Sincerely,
- * Document Control Desk LR-N970449
Attachment
4 C Mr. Hubert J. Miller, Administrator
-Region I U. s. Nuclear Regulatory
Commission
.475 Allendale
Road King of Prussia, PA 19406 JUL 16 1997 Mr. L. N. Olshan, Licensing
Project Manager -Salem U. S. Nuclear Regulatory
Commission
One White Flint North 11555 Rockville
Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall
-Salem (X24) USNRC Senior Resident Inspector
Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering
33 Arctic Parkway CN 415 Trenton, NJ 08625 95-4933
ATTACHMENT
I LR-N970449
NOTICE OF VIOLATION
Public Service Electric & Gas Company Docket No:
Salem Nuclear Generating
Station License No: DPR-75 Unit 2 During an NRC inspection
conducted
on March 1 to April 12, 1997, violations
of NRC requirements
were identified.
In accordance
with the "General Statement
of Policy and Procedure
for NRC Enforcement
Actions." NUREG-1600, the violations
are listed below: Appendix B, Criterion
V of 10 CFR 50 requires that activities
affecting
quality be prescribed
by procedures
and shall be accomplished
in accordance
with those procedures.
Procedure
NC.DE-AP.ZZ-0012(Q), "Test Program", Revision 6, Section 5.2.c requires testing to be conducted
with approved step-by-step
Special Test Procedures, existing procedures, or standards.
Section 5.2.e requires recording
test data on data sheets . * Section 5.2.f requires evaluating
test results to ensure they are acceptable
prior to restoring
plant equipment.
- Contrary to the above, post-modification
test procedures
for Salem cdntrol room area air conditioning
system (CAACS) were not followed, required.data
was not recorded, and plant equipment
was restored with test results outside established
acceptance
criteria, as evidenced
by the following
examples:
1. Procedure
lEC-3505 package No. 1 STP-2, Revision 2, *control Area Air Conditioning
System (CAACS) and Emergency
Air Conditioning
System (EACS) Coil Test Procedure (to verify heat transfer capability
of Unit 1 CAACS and Unit 1 EACS cooling coil units), steps 5.5.3.7 and 5.5.4.7 required the initiation
of an Action Request (AR) to clean the coils if the coil appearance
was not "bare metal or shiny appearance".
The condition
of the coil for 1HVE200, recorded on Attachment
7.12 was" ... covered with white chalky film ... " and an AR to clean the coil was not initiated . 1
ATTACHMENT
I LR-N970449
2. Procedure
lEC-3505 Package No. 1, STP-4, Revision 3, Control Area Ventilation (CAV) Leakage Test [for leak testing the ductwork and filter housing which have the potential
for leakage into the control room pressure boundary], attachment
7.3 establishes
EACS charcoal filter housing and duct maximum allowable
leakage test acceptance
criteria of 8.0 cubic feet per minute (cfm). Actual leakage rates recorded were 10.78 cfm for Unit 1 and 10.59 cfm for Unit 2. Both recorded leakage rates were outside the established
acceptance
criteria, but the test results were approved and the EACS system was restored to service. 3. Procedure
lEC-3505 Package No. 1 STP-4, Revision 3, attachment
7.3 requires an EACS charcoal filter housing and duct test pressure of 4.0 inches water column (inwc). Based on the atmospheric
pressure recorded in inches of mercury (inHg) and initial boundary pressures
in pounds per square foot (psf) absolute (abs.), the test pressures
were less than the required 4 inwc. 4. Procedure
lEC-3505 Package No. 1
Revision 3, Appendix A, steps 2.e and 2.h require recording
the initial and final times of the test. The times were not recorded.
5. Procedure
lEC-3505 Package No. 1, STP-4, Revision 3, Step 5.6.1, requiring
review of test data by the test engineer was incorrectly
deleted by Modification
Concern and Resolution
297. This is* a Severity Level IV problem (Supplement
1). 2
ATTACHMENT
II SUPPLEMENTAL
RESPONSE TO NOTICE OF VIOLATION
SALEM GENERATING
STATION UNIT 2 LR-N970449
"1. Procedure
lEC-3505 package No. 1 STP-2,
2, Control Area Air Conditioning
System (CAACS) and Emergency
Air Conditioning
System (EACS) Coil Test Procedure (to verify heat transfer capability
of Unit 1 CAACS and Unit 1 EACS cooling coil units), steps 5.5.3.7 and 5.5.4.7 required the initiation
of an Action Request (AR) to clean the coils if the coil appearance
was not "bare metal or shiny appearance".
The condition
of the coil for 1HVE200, recorded on Attachment
7.12 was" ... covered with white chalky film ... " and an AR to clean the coil was not initiated." (1) The reason for the violation.
The root cause for the violation
was provided in LR-N970371, dated June 30, 1997, and restated below for completeness; "The reason for the violation
was poor human performance
by the *CAV project team and testing personnel
and management
oversight.
Personnel
involved failed to meet PSE&G's standard of procedural
compliance.
Personnel
did not properly revise CAV Special Test Procedures (STPs) in accordance
with PSE&G procedures
to reflect changes in testing methodology
and acceptance
criteria.
In addition inadvertent
removal of the test engineer acceptance
signoff by the project team is an example of inattention
to detail. PSE&G management
also did not provide an adequate level of management
oversight
of personnel
preparing.and
implementing
the CAV_Special
Test Procedures." * (2) The corrective
steps that have been taken. 1. AR 970320247
was issued to evaluate the white chalky film observed on the coil. The white chalky film (lead oxide) observed on the coil was the result of chemical cleaning of the EACS coil by the vendor. This white chalky substance
was evaluated
and determined
to have no effect on the heat transfer characteristic
of the coil . 1
II SUPPLEMENTAL
RESPONSE TO NOTICE OF VIOLATION
SALEM GENERATING
STATION UNIT 2 LR-N970449
2. The design change test procedure
acceptance
criterion
was revised as per the above evaluation
and vendor recommendation.
3. LR-N970371, dated June 30, 1997, -contains
additional
information.
(3) The corrective
steps that will be taken to avoid further violations.
LR-N970371, dated June 30, 1997, contains the required information.
(4) The date when full compliance
will be achieved.
PSE&G achieved compliance
when the AR 970320247
was issued. LR-N970371, dated June 30, 1997, contains additional
information . 2
- ATTACHMENT I I SUPPLEMENTAL
RESPONSE TO NOTICE OF VIOLATION
SALEM GENERATING
STATION UNIT 2 LR-N970449
"2. Procedure
lEC-3505 Package No. 1, STP-4, Revision 3, Control Area Ventilation (CAV) Leakage Test [for leak testing the ductwork and filter housing which have the potential
for leakage into the control room pressure * boundary], attachment
7.3 establishes
EACS charcoal filter housing and duct maximum allowable
leakage test acceptance
criteria of 8.0 cubic feet per minute (cfm). Actual leakage rates recorded were 10.78 cfm for Unit 1 and 10.59 cfm for Unit 2. Both recorded leakage rates were outside the established
acceptance
criteria, but the test results were approved and the EACS system was restored to service." (1) The reason for the violation.
The root cause for the violation
was provided in LR-N970371, dated June 30, 1997, and restated below for completeness; "The reason for the violation
was poor human performance
by the CAV project team and testing personnel
and management
oversight.
Personnel
involved failed to meet PSE&G's standard of procedural
compliance.
Personnel
did not properly revise CAV Special Test Procedures (STPs) in accordance
with PSE&G procedures
to reflect changes in testing methodology
and acceptance
criteria.
In addition inadvertent
removal of the test engineer acceptance
signoff by the project team is an example of inattention
to detail. PSE&G management
also did not provide an adequate level of management
oversight
of personnel
preparing
and implementing
the CAV Special Test Procedures." (2) The corrective
steps that have been taken. 1. Engineering
Evaluation
S-C-SC-MEE-1212, Control Area Ventilation:
Review of CREACS Filter Housing Test Requirements
and Acceptance
Criteria, issued on May 30, 1997, evaluated
the recorded leakage rate acceptable.
2. Modification
Concern and Resolution (MCR) 193 to the design change test procedure
revised the leakage rate 3
II SUPPLEMENTAL
RESPONSE TO NOTICE OF VIOLATION
SALEM GENERATING
STATION UNIT 2 LR-N970449
acceptance
criterion
based on Control Room Dose Calculation
and was evaluated
in Engineering
Evaluation
S-C-SC-MEE-1212.
3. LR-N970371, dated June 30, 1997, contains additional
information.
(3) The corrective
steps that will be taken to avoid further violations.
LR-N970371, dated June 30, 1997, contains the required information.
(4) The date when full compliance
will be achieved.
PSE&G achieved compliance
when the Engineering
Evaluation
was issued demonstrating
that the recorded leakage rate was acceptable, and MCR 193 to lEC-3505 revised the leakage rate acceptance
criterion.
LR-N970371, dated June 30, 1997, contains additional
information . 4
II SUPPLEMENTAL
RESPONSE TO NOTICE OF VIOLATION
SALEM GENERATING
STATION UNIT 2 LR-N970449
"3. Procedure
lEC-3505 Package No. 1 STP-4, Revision 3, attachment
7.3 requires an EACS charcoal filter housing and duct test pressure of 4.0 inches water column (inwc). Based on the atmospheric
pressure recorded in inches of mercury (inHg) and initial boundary pressures
in pounds per square foot (psf) absolute (abs.), the test pressures
were less than the required 4 inwc." (1) The reason for the violation.
The root cause for the violation
was provided in LR-N970371, dated June 30, 1997, and restated below for completeness; "The reason for the violation
was poor human performance
by the CAV project team and testing personnel
and management
oversight.
Personnel
involved failed to meet PSE&G's standard of procedural
compliance.
Personnel
did not properly revise CAV Special Test Procedures (STPs) in accordance
with PSE&G procedures
to reflect changes in testing methodology
and acceptance
criteria.
In addition inadvertent
removal of the test engineer acceptance
signoff by the project team is an example of inattention
to detail. PSE&G management
also did not provide an adequate level of management
oversight
of personnel
preparing
and implementing
the CAV Special Test Procedures." (2) The corrective
steps that have been taken. 1. Engineering
Evaluation
S-C-SC-MEE-1212, Control Area *ventilation:
Review of CREACS Filter Housing Test Requirements
and Acceptance
Criteria, issued on May 30, 1997, evaluated
the higher initial test pressures
and accepted the test data. 2. The HEPA and Charcoal Filter Housing decay calculations
were revised with acceptable
results. 3. The test procedure
acceptance
criteria was revised. 4. LR-N970371, dated June 30, 1997, contains additional
information . 5
ATTACHMENT
II SUPPLEMENTAL
RESPONSE TO NOTICE OF VIOLATION
SALEM GENERATING
STATION UNIT 2 LR-N970449
(3) The corrective
steps that will be takeri to avoid further violations.
dated June 30, 1997, contains the required information.
(4) The date when full compliance
will be achieved.
PSE&G achieved compliance
when the Engineering
Evaluation
was issued determining
that the higher recorded test pressures
were acceptable, the test procedure
acceptance
criteria was revised, and the HEPA and Charcoal Filter Housing decay calculations
were revised. LR-N970371, dated June 30, 1997, contains additional
information . * 6
I ---.. ATTACHMENT I I SUPPLEMENTAL
RESPONSE TO NOTICE OF VIOLATION
SALEM GENERATING
STATION UNIT 2 LR-N970449
"4. Procedure
lEC-3505 Package No. 1 STP-4,
3, Appendix A, steps 2.e and 2.h require recording
the initial and final times of the test. The times were not recorded." (1) The reason for the violation.
The root cause for the violation
was provided in LR-N970371, dated June 30, 1997, and restated below for completeness; "The reason for the violation
was poor human performance
by the CAV project team and testing personnel
and management
oversight.
Personnel
involved failed to meet PSE&G's standard of procedural
compliance.
Personnel
did not properly revise CAV Special Test Procedures (STPs) in accordance
with PSE&G procedures
to reflect changes in testing methodology
and acceptance
criteria.
In addition inadvertent
removal of *the test engineer acceptance
signoff by the project team is an example of inattention
to *detail. PSE&G management
also did not provide an adequate level of management
oversight
of personnel
preparing
and implementing
the CAV Special Test Procedures." (2) The corrective
steps that have been taken. 1. The test engineers
responsible
have been counseled
and advised of the importance
of strict procedure
compliance.
Although the start and finish time were not recorded and cannot be retrieved, the total test duration time was *recorded, which was the only value necessary
for the required calculation.
2. LR-N970371, dated June 30, 1997, contains additional
information.
(3) The corrective
steps that will be taken to avoid further violations.
LR-N970371, dated June 30, 1997, contains the required information . * 7
... ATTACHMENT
II SUPPLEMENTAL
RESPONSE TO NOTICE OF VIOLATION
SALEM GENERATING
STATION UNIT 2 LR-N970449
(4) The date when full compliance
will be achieved.
PSE&G achieved compliance
when the test was completed
satisfactorily.
Although the start and finish time were not recorded and cannot be retrieved, the total test duration time was recorded, which was the only value necessary
for the required calculation.
LR-N970371, dated June 30, 1997, contains the required information.
"5. Procedure
lEC-3505 Package No. 1, STP-4, Revision 3, Step 5.6.1, requiring
review of test data by the test engineer was incorrectly
deleted by Modification
Concern and Resolution
297." (1) The reason for the violation.
The root cause for the violation
was provided in LR-N970371, dated June 30, 1997, and restated below for completeness; "The reason for the violation
was poor human performance
by the CAV project team and testing personnel
and management
oversight.
Personnel
involved failed to meet PSE&G's standard of procedural
compliance.
Personnel
did not properly revise CAV Special Test Procedures (STPs) in accordance
with PSE&G procedures
to reflect changes in testing methodology
and acceptance
criteria.
In addition inadvertent
removal of the test engineer acceptance
signoff by the project team is an example of inattention
to detail. PSE&G management
also did not provide an adequate level of management
oversight
of personnel
preparing
and implementing
the CAV Special Test Procedures." (2) 1. 2. 3. * The corrective
steps that have been taken. The test engineer responsible
for removing the procedure
step was counseled.
A review signature
was added for a level III sign off of test results. The test results were reviewed by a level III test engineer . 8
_, *-I l ... * * ATTACHMENT I I SUPPLEMENTAL
RESPONSE TO NOTICE OF VIOLATION
SALEM GENERATING
STATION UNIT 2 LR-N970449
4. LR-N970371, dated June 30, 1997, contains additional
information.
(3) The corrective
steps that will be taken to avoid further violations.
LR-N970371, dated June 30, 1997, contains the required information.
(4) The date when full compliance
will be achieved.
PSE&G achieved compliance
when a review signature
was added for a level III sign off of test results and the test results were reviewed by a level III test engineer.
LR-N970371, dated June 30, 1997, contains additional
information . 9