ML17309A506

1992 Rept of Facility Changes,Tests & Experiments Conducted W/O Prior Approval for Aug 1991 Through Jul 1992. W/921218 Ltr

ML17309A506
Person / Time
Site:	Ginna
Issue date:	07/31/1992
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9212300186
Download: ML17309A506 (178)

Text

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ACCESSION NBR:9212300186 DOC.DATE: 92/07/31 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Project Directorate I-3

SUBJECT:

"1992 Rept of Facility Changes, Tests & Experiments Conducted w/o Prior Approval for Aug 1991 Through Jul 1992." W/921218 D ltr.

DISTRIBUTION CODE: IE47D COPIES RECEIVED:LTR J ENCL) SIZE: /5P TITLE: 50.59 Annual Report of Changes, Tests or Experiments Made W out Approv NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD1-3 LA 1 0 PD1-3 PD 5 5 JOHNSONiA 1 0 D INTERNAL: AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 NRR - LHFBll 1 1 NRR/DOEA/OEAB11 1 1 EG FI 02 1 1 RGN1 FILE 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D

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NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 13

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ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 'I4649-0001 Tfi,tP<ONf ARLa CODC 7>5 546 2700 December 18, 1992 U.S. Nuclear Regulatory Commission Document Control Desk ATTN: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Annual Report of Facility Changes, Tests, and Experiments Conducted Without Prior Commission Approval R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

The subject report is hereby submitted as required by 10 CFR 50.59(b). Enclosed are the original and one copy of the report containing descriptions and summaries of the safety evaluations conducted in support of changes to the facility and procedures described in the UFSAR and special tests, from August 1990 through July 1991.

Very truly yours, Robert C. Mecredy Vice President Ginna Nuclear Production RCM/lms Enc.

xc: Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I Allendale Road 475 King of Prussia, PA 19406 )[9 Ginna Senior Resident Inspector 921230018b cy20731 PDR ADOCK 05000244 PD Xpp R

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~ -9212300186 1992 REPORT OF FACILITY CHANGES, TESTS AND EXPERIMENTS CONDUCTED WITHOUT PRIOR APPROVAL FOR AUGUST 1991 THROUGH JULY 1992 SECTION A COMPLETED ENGINEERING WORK REQUESTS (EWR) AND TECHNICAL STAFF REQUESTS (TSR)

SECTION B COMPLETED STATION MODIFICATIONS (SM)

SECTION C TECHNICAL EVALUATIONS (TE)

SECTION D TEMPORARY MODIFICATIONS SECTION E PROCEDURE CHANGES SECTION F COMPLETED SPECIAL TESTS (ST) AND EXPERIMENTS R.E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 ROCHESTER GAS AND ELECTRIC CORPORATION DATED DECEMBER 18, 1992

SECTION A COMPLETED ENGINEERING WORK REQUESTS (EWRs)

AND TECHNICAL STAFF REQUESTS (TSRs)

This section contains a description of modifications in the facility as described in the safety analysis report, and a summary of the safety evaluation for those changes, pursuant to the requirements of 10 CFR 50.59(b).

The basis for inclusion of an EWR or TSR in this section is closure of the completed modification package in the Document Control Department.

EWR-14 05 MODIFICATIONS TO THE PLANT SECURITY SYSTEM THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES THE UPGRADE OF THE PLANT SECURITY SYSTEM. INFORMATION CONCERNING SPECIFICS OF THIS MODIFICATION ARE CONSIDERED SAFEGUARDS INFORMATION, AND WILL BE ADMINISTRATIVELYCONTROLLED UNDER CURRENT GS PROCEDURES.

REVISION 1 TO THIS DESIGN CRITERIA AND SAFETY ANALYSIS INCORPORATES THE CHANGES TO DOOR f44 WHICH WILL BRING THE INVOLVED SECURITY AREA INTO COMPLIANCE WITH THE EXISTING ACCESS CONTROL SYSTEM.

REVISION 2 TO THIS DESIGN CRITERIA AND SAFETY ANALYSIS INCLUDES ADDING POSITION "ALARM SWITCHES AND ASSOCIATED CONDUIT TO FIRE DOORS F12~ F13~ F14'ND F15'HICH ACCESS THE TECHNICAL SUPPORT CENTER AT THE SOUTH AND NORTH ENDS. THE TURBINE BUILDING MEZZANINE TO THE TECHNICAL SUPPORT CENTER NORTH HALL, AND THE TURBINE BUILDING MEZZANINE NORTHWEST TO THE SERVICE BUILDING. THIS IS BEING DONE DUE TO PRESSURE DIFFERENTIALS THAT EXIST WHEN THE TURBINE BUILDING EXHAUST FANS ARE ACTIVATED, WHEREAS THESE FIRE DOORS ARE NOT ABLE TO CLOSE AND LATCH PROPERLY. THEREFORE, THE ADDED POSITION ALARMS ALLOW FOR ADMINISTRATIVE CONTROLS TO BE PLACED UPON THESE FIRE DOORS.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND THE EVENTS REQUIRING ANALYSIS BY USNRC REG.

GUIDE 1.70. THE EVENTS RELATED TO THIS MODIFICATION INCLUDE (1)

FIRES AND APPENDIX R LEVELS OF PROTECTION FROM FIRES) (2) SECURITY.

THE TYPES OF ACCIDENTS AND THEIR CONSEQUENCES AS EVALUATED IN THE UFSAR ARE UNAFFECTED BY THIS MODIFICATION.

THE SECURITY SYSTEM IS POWERED FROM A NON-SAFEGUARDS BUS WITH BACKUP FROM A POWER SOURCE DEDICATED TO THE SECURITY SYSTEM.

SEI SMIC CATEGORY I SYSTEMS g STRUCTURES g OR COMPONENTS ARE ONLY AFFECTED BY MODIFICATIONS TO THE ACCESS CONTROL SYSTEMS, AND THE DESIGN CRITERIA REQUIRES THAT SAFETY RELATED STRUCTURES'YSTEMS'ND COMPONENTS ARE IN NO WAY DEGRADED.

FIRE PROTECTION REQUIREMENTS FOR THIS MODIFICATION SHALL BE MET AS OUTLINED IN THE DESIGN CRITERIA. THEREFORE, THERE WILL BE NO INCREASE IN FIRE LOADING OR FIRE HAZARD, AND NO EXISTING EQUIPMENT REQUIRED TO MEET 10CFR50 APPENDIX R REQUIREMENTS WILL BE AFFECTED.

INTERIM MEASURES DURING CONSTRUCTION ACTIVITIES WILL BE ADMINISTRATIVELY CONTROLLED TO PREVENT DEGRADATION OF FIRE AND SECURITY BARRIERS.

THUS, THIS MODIFICATION DOES NOT AFFECT ANY SAFEGUARDS EQUIPMENT NOR DOES ZT AFFECT THE OPERATION OF SUCH EQUIPMENT. THIS MODIFICATION NEITHER INCREASES THE CONSEQUENCES'OR DOES IT REDUCE THE MARGINS OF SAFETY FOR:

1. FIRE PROTECTION FEATURES

2. PLANT SECURITY BASED UPON A REVIEW OF THE UFSAR AND THE REQUIREMENTS OF GINNA STATION TECHNICAL SPECIFICATIONS, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR-1660B RCS OVERPRESSURE PROTECTION PHASE 2 THIS ENGINEERING WORK REQUEST ADDRESSES THE REPLACEMENT OF CHECK VALVES FOR THE RCS OVERPRESSURE PROTECTION - PHASE 2.

A REVIEW HAS BEEN PERFORMED OF ALL EVENTS ANALYZED IN THE GINNA STATION UPDATED FINAL SAFETY ANALYSIS REPORT. THE EVENTS RELATED TO THIS MODIFICATION ARE:

1) FIRES

2) SEISMIC EVENTS

3) INADVERTENT OPENING OR FAILURE TO CLOSE OF A PRESSURIZER PORV

4) EFFECT ON THE LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) SYSTEM THE MODIFICATION WILL NOT INCREASE THE PROBABILITY OF, OR THE EFFECTS OF, A FIRE SINCE THE MATERIALS USED WILL MEET CRITERIA EQUAL TO OR GREATER THAN THOSE PRESENTLY INSTALLED.

THE REPLACEMENT CHECK VALVES WILL CONTINUE TO BE SEISMICALLY SUPPORTED AND THEREFORE WILL NOT AFFECT SAFETY-RELATED EQUIPMENT.

THE MODIFICATION WILL NOT ALTER THE CURRENT OPERATION OF THE INSTRUMENT AIR SYSTEM OR THE NITROGEN ACCUl6JLATOR SYSTEM AND WILL NOT INCREASE THE PROBABILITY OF AN EVENT ASSOCIATED WITH THE INADVERTENT OPENING OR FAILURE TO CLOSE OF A PRESSURIZER PORV.

THE MODIFICATION WILL NOT AFFECT THE NITROGEN SUPPLY TO THE LTOP SYSTEM. NEITHER THE NITROGEN QUANTITY NOR THE NITROGEN PRESSURE WILL BE AFFECTED BY THE INSTALLATION OF THE CHECK VALVES. THE PERFORMANCE REQUIREMENTS OF THE PRESSURIZER PORV ACTUATION LINES ENSURE THAT THE ASSUMPTIONS USED ZN THE LTOP EVALUATION ARE NOT VIOLATED. THEREFORE, LTOP IS NOT AFFECTED BY THIS MODIFICATION.

BASED ON THE ABOVE ANALYSIS-A ALL SAFETY REQUIREMENTS ARE MET AND THE MODIFICATION IS IN ACCORDANCE WITH THE GINNA STATION LICENSING DESIGN BASIS.

B. THE MARGIN OF SAFETY DURING NORMAL OPERATING AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION ARE NOT REDUCED.

C. THE STRUCTURES, SYSTEMS'ND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS ARE ADEQUATE.

BASED UPON A REVIEW OF THE UFSAR AND THE REQUIREMENTS OF GINNA STATION TECHNICAL SPECIFICATIONS'T HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR-3341 DC FUSE COORDINATION THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES THE UPGRADE OF THE 125 VOLT DC DISTRIBUTION SYSTEM.

REVISION 4 TO THIS DESIGN CRITERIA AND SAFETY ANALYSIS ADDRESSES THE TRANSFER OF LOADS FROM ONE FUSE/SWITCH POSITION TO ANOTHER IN THE SAME DC DISTRIBUTION PANEL.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND THE EVENTS REQUIRING ANALYSIS BY USNRC REGULATORY GUIDE 1 70. THE EVENTS RELATING TO THIS MODIFICATION ARE: (1)

LOSS OF DC CONTROL POWER, (2) NATURAL EVENTS (FIRE AND EARTHQUAKE)

AND (3) UFSAR CHAPTER 15 ACCIDENTS AND TRANSIENTS.

THE FIRST EVENT THAT HAS BEEN ANALYZED IS THE LOSS OF DC CONTROL POWER. THE PRIMARY PURPOSE OF THE PROPOSED FUSE CHANGES ARE TO INSURE THAT THE FUSES SUPPLYING CLASS 1E LOADS WILL DO SO UNDER ALL DESIGN BASIS CONDITIONS. IN ADDITION, THE PROPOSED FUSES THAT SUPPLY NON CLASS 1E LOADS WILL FUNCTION AS ISOLATION DEVICES.

THAT IS, THEY WILL CLEAR ANY FAULT OR OVERLOAD CONDITION WITHOUT CAUSING THE LOSS OF THE SAFEGUARD LOADS ON THE SYSTEM. THIS WILL BE ACCOMPLISHED THROUGH PROPER FUSE COORDINATION AS DESCRIBED IN THE DESIGN CRITERIA. THEREFORE, AVAILABILITY,OF THE CLASS 1E DC DISTRIBUTION SYSTEM IS NOT DEGRADED.

NATURAL EVENTS AND CHAPTER 15 ACCIDENT/TRANSIENT ANALYSES.

THE FUSES SELECTED TO REPLACE EXISTING FUSES WILL BE SIZED TO CLEAR MAXIMUM,FAULT CURRENTS AT RATED VOLTAGE AS WELL AS ENSURE SYSTEM OPERABILITY. THEREFORE, THE FUSES WILL BE ABLE TO PERMIT THE PROPER FUNCTIONING OF THE SAFETY SYSTEMS USED TO MITIGATE UFSAR CHAPTER 15 ACCIDENTS AND TRANSIENTS. IN ADDITION, CORRECTLY SIZED FUSES WILL INSURE THAT SUSTAINED ARCING WILL NOT OCCUR DURING FAULT CONDITIONS. THEREFOREi THE CONSEQUENCES OF A FIRE IS NOT INCREASED.

ANY ADDITIONAL WIRING FOR TRANSFERRING THE SUPPLY TO A CIRCUIT FROM ONE FUSE/SWITCH POSITION TO ANOTHER WILL USE CABLE IN COMPLIANCE WITH IEEE 383-1974 FLAME TEST. SUCH CABLE WILL BE ONLY WITHIN A DC DISTRIBUTION PANEL AND THUS WILL NOT INCREASE THE FIRE LOADING IN THE AREA.

ALL FUSES USED ON THE 125VDC DISTRIBUTION SYSTEM WILL BE SHOWN TO FUNCTION WITHOUT DISCONTINUITYi CONSISTENT WITH THE SEISMIC TESTING REQUIREMENTS OF GOULD INC., FUSE QUALIFICATION SPECIFI CATION FOR CLASS 1E EQUIPMENT i GEFD 00 1 i REVISION B i DECEMBER, 1981 IN ADDITION, FUSE CLIPS AND REDUCERS WILL BE I I I I S ZED CONS STENT W TH MANUFACTURER S REQU REMENTS ~ THEREFORE i THERE IS NO SIGNIFICANT INCREASE IN FUSE FAILURES DUE TO A SEISMIC EVENT.

SECTION 12.1 OF THE DESIGN CRITERIA ALLOWS THE USE OF EXISTING FUSES IN THE DC SYSTEM PROVIDED THEY ARE OF THE CORRECT SIZE AND TYPE SPECIFICALLY, EXISTING FUSES MEETING ALL SYSTEM COORDINATION REQUIREMENTS AS DESCRIBED IN SECTION 17.0 OF THE DESIGN CRITERIA AND HAVING BEEN EVALUATED FOR USE IN CLASS 1E APPLICATIONS DO NOT REQUIRE REPLACEMENT. BASED UPON THE RESULTS OF THE TESTING PROGRAM FOR NEW FUSES, THE RELIABILITY OF THE EXISTING FUSES IS DETERMINED TO BE APPROPRIATE FOR CONTINUED USE IN THE DC SYSTEM.

THEREFORE i BASED UPON THE ABOVE ANALYSES g IT HAS BEEN DETERMINED THAT:

(A) THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION ARE NOT REDUCED AND (B) I THE STRUCTURES i SYSTEMS g AND COMPONENTS PROV DED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS ARE ADEQUATE.

THE PROBABILITY OF OCCURRENCE AND THE CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY PREVIOUSLY EVALUATED IN THE SAFETY ANALYSIS REPORT ARE NOT INCREASED.

THE POSSIBILITY OF AN ACCIDENT OR MALFUNCTION OF A TYPE DIFFERENT FROM ANY PREVIOUSLY EVALUATED IN THE SAFETY ANALYSIS HAS NOT BEEN CREATED.

THE MARGIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION IS NOT REDUCED.

EWR-3505 MODERNIZATION OF STATION 13A THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES THE MODERNIZATION OF STATION 13A IN ORDER TO MEET MINIMUM REQUIREMENTS FOR RELIABILITY AND SECURITY AS DEVELOPED IN THE NORTHEAST POWER COORDINATING COUNCIL AND NEW YORK POWER POOL RELIABILITY CRITERIA AS IT APPLIES TO PROTECTIVE RELAYS.

REVISION 2 TO THIS DESIGN CRITERIA AND SAFETY ANALYSIS IS BASICALLY THE REPLACEMENT OF THE RELAYS FOR CIRCUITS 911 AND 912 WITH NEW STATIC DISTANCE PROTECTION TYPES'SED AS A SECONDARY PROTECT ION SYSTEMS THESE MODELS g THE QUADRAMHO g MANUFACTURED BY GEC MEASUREMENTS, INCORPORATE A "WEAK IN FEED FEATURE" THAT PERMITS OPERATION OF THE RELAY WITH A WEAK SUPPLY SOURCE.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND THE EVENTS REQUIRING ANALYSIS BY USNRC REG.

GUIDE 1.70. EVENTS RELATED TO THIS MODIFICATION ARE AS FOLLOWS-

1) LOSS OF EXTERNAL LOAD

2) LOSS OF OFFSITE POWER THE LOSS OF EXTERNAL LOAD HAS BEEN ANALYZED IN THE GINNA UFSAR.

THIS MODIFICATION DOES NOT EFFECT THE RESULTS OF THAT ANALYSIS IN ADDITION, THIS MODIFICATION WILL INCREASE THE REDUNDANCY AND SEPARATION OF EXISTING PROTECTIVE RELAY SYSTEMS FOR THE 115 KV LINES. THUS THIS MODIFICATION DOES NOT INCREASE THE PROBABILITY OF A LOSS OF EXTERNAL LOADS. THE POWER CONTROL SCHEME WILL NOT BE MODIFIED IN ANY WAY THIS MODIFICATION WILL INCREASE THE REDUNDANCY AND SEPARATION OF THE EXISTING PROTECTIVE RELAYING FOR THE OFFSITE POWER SOURCES.

THE POWER CONTROL SCHEME WILL NOT BE MODIFIED IN ANY WAY. THUS THIS MODIFICATION DOES NOT INCREASE THE PROBABILITY OF A LOSS OF OFFSITE POWER.

BASED UPON A REVIEW OF THE UFSAR, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR-4 04 3 INCORPORATION OF KEYPHASOR PROXIMITY TRANSDUCERS INTO RCP VIBRATION MONITORING SYSTEM THIS EWR (ENGINEERING WORK REQUEST) ADDRESSES THE INCORPORATION OF A KEYPHASOR PROXIMITY TRANSDUCER INTO THE RCP VIBRATION MONITORING SYSTEM OF EACH RCP. EACH KEYPHASOR PROXIMITY TRANSDUCER WILL PROVIDE RCP VIBRATION DATA VALUABLE FOR DIAGNOSTIC TESTING PURPOSES. THERE ARE NO CONTROL FUNCTIONS ASSOCIATED WITH THIS MODIFICATION..

REVISION 0, OF THE DESIGN CRITERIA AND SAFETY ANALYSIS WERE PRESENTED AND APPROVED BY PORC ON JANUARY 24, 1985, PORC ITEM NUMBER 6.1.0-85-009-001.

UNDER REVISION 1 g PARAGRAPHS 1 ~ 1 g 1 ~ 3 g 8 ~ 0 g AND 23 ~ 1 OF THE DESIGN CRITERIA HAVE BEEN REVISED TO INCLUDE SEISMIC REQUIREMENTS FOR THE INSTALLATION OF NEW CONDUIT AND/OR ENCLOSURES LOCATED IN THE VICINITY OF SEISMIC CATEGORY 1 EQUIPMENT WILL BE INSTALLATED IN ACCORDANCE WITH REGULATORY GUIDE 1.29 SECTION C.2.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION FSAR AND THE EVENTS REQUIRING ANALYSIS BY USNRC REGULA-TORY GUIDE 1.70. THE EVENTS RELATED TO THIS MODIFICATION ARE MAJOR AND MINOR FIRES AND SEISMIC EVENTS.

BASED UPON THE ANALYSES DESCRIBED UNDER PARAGRAPH 3.1 TO 4.4 OF THE SAFETY ANALYSIS'T HASg THEREFOREJ BEEN DETERMINED THAT ADEQUATE MARGINS OF SAFETY EXIST DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION, AND THERE ARE ADEQUATE STRUCTURES, SYSTEMS AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS.

EWR-4067 115 KV BENCHBOARD MODIFICATION THIS EWR (ENGINEERING WORK REQUEST) ADDRESSES THE MODIFICATION WHICH INVOLVES THE REPLACEMENT OF THE EXISTING (9 SECTIONS) 115 KV BENCHBOARD FROM THE CONTROL ROOM. ALL DIRECT BREAKER CONTROL FEATURES, NOW LOCATED ON THE 115 KV BENCHBOARD WILL BE REMOVED.

EXISTING BREAKER CONTROL SWITCHES ON THE MCB WILL BE UNAFFECTED BY THIS MODIFICATION. THE 9 SECTION 115 KV BENCHBOARD WILL BE REPLACED WITH A STATUS DISPLAY PANEL. THE STATUS DISPLAY PANEL WILL BE ADDED TO THE MCR AND WILL PROVIDE STATUS LIGHTS ASSOCIATED WITH BREAKER POSITIONS LOCATED AT SUBSTATION 13A.

REVISION 0 OF THE DESIGN CRITERIA AND SAFETY ANALYSIS WERE PRESENTED AND APPROVED BY PORC ON JANUARY 30'985'ORC ITEM NUMBER 6.1.0-85-011-003.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION FSAR AND THE EVENTS REQUIRING ANALYSIS BY USNRC REGULATORY GUIDE 1.70. THE EVENTS RELATED TO THIS MODIFICATION ARE: 1)

SEISMIC EVENTSi 2) MAJOR AND MINOR FIRES') LOSS OF EXTERNAL ELECTRICAL LOAD AND 4) LOSS OF OFFSITE A.C. POWER.

BASED UPON THE ANALYSES DESCRIBED UNDER PARAGRAPH 3.1 TO 4.4 OF THE SAFETY ANALYSIS'T HAS THEREFORE'EEN DETERMINED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND FOR THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED.

tl" EWR-4265 CONTAINMENT THIS POST ACCIDENT 1A & 1B CHARCOAL FILTER EWR (ENGINEERING WORK REQUEST) ADDRESSES THE MODIFICATION SYSTEMS WHICH MODIFIED THE A AND B TRAIN CONTAINMENT RECIRCULATION SYSTEMS.

IN THE EVENT OF A LARGE BREAK LOCA SCENARIO i THERE IS THE POTENTIAL FOR THE A AND B TRAIN CONTAINMENT RECIRCULATION CHARCOAL FILTER FAN SYSTEM OPERABILITY TO BE SEVERELY RESTRICTED DUE TO THE FLOODING OF THE SYSTEM DUCTWORK LOCATED IN THE BASEMENT OF CONTAINMENT.

THE PURPOSE OF THIS MODIFICATION IS TO UPGRADE THE A AND B TRAIN CONTAINMENT RECIRCULATION SYSTEMS TO ENSURE ADEQUATE AIR DISTRIBUTION OF THE RECIRCULATION AIR THROUGH THE CHARCOAL FILTERS TO THE CONTAINMENT VESSEL OPERATING FLOOR.

IN ORDER TO ENSURE ADEQUATE AIR DISTRIBUTION OF THE RECIRCULATION AIR THROUGH THE CHARCOAL FILTERS TO THE OPERATING FLOOR, SIX (6)

ADDITIONAL AIR DISCHARGE OPENINGS ARE TO BE ADDED TO THE 1A AND 1B POST ACCIDENT CHARCOAL FILTER DISCHARGE DUCTWORK.

ALL OF THE OPENINGS ARE TO BE ON THE DISCHARGE SIDE OF THE CHARCOAL FILTERS AND BEFORE THE LOCATION OF THE DUCTWORK WHICH COULD POTENTIALLY FLOOD AND. RESTRICT THE DELIVERY OF THE AIR TO THE CONTAINMENT OPERATING FLOOR.

ALL OF THE OPENINGS ARE TO BE LOCATED ABOVE THE CONTAINMENT OPERATING FLOOR IN ORDER TO ENSURE ADEQUATE DELIVERY OF THE FILTERED AIR TO THIS AREA.

REVISION 0 OF THE DESIGN CRITERIA AND SAFETY ANALYSIS WAS PRESENTED AND APPROVED BY PORC ON APRIL 29, 1987 PORC NUMBER 6.1.0-87-068-001.

THE PURPOSE OF REVISION 1 OF THE DESIGN CRITERIA AND SAFETY ANALYSIS IS TO CORRECT TYPOGRAPHICAL ERRORS IN REVISION 0-

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION FSAR AND THE EVENTS REQUIRING ANALYSIS BY USNRC REGULATORY GUIDE 1.70. THE EVENTS RELATED TO THIS MODIFICATION ARE LISTED AS FOLLOWS:

1) INTERNAL AND EXTERNAL EVENTS SUCH AS I F RE g FLOODS g STORMS, AND EARTHQUAKES ~

2) SYSTEM FUNCTIONAL OPERATION DURING A LOCA SCENARIO.

BASED UPON THE ANALYSES DESCRIBED UNDER PARAGRAPHS 3.1 TO 4.4 OF THE SAFETY ANALYSIS'T HAS THEREFOREi BEEN DETERMINED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN DETERMINED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR-4514 STATION 13A FIBER OPTIC COMMUNICATIONS SYSTEM THIS EWR (ENGINEERING WORK REQUEST) ADDRESSES THE INSTALLATION OF FIBER OPTIC COMMUNICATION EQUIPMENT AT THE STATION 13 RADIO TOWER AND AT STATION 13A AND FIBER OPTIC CABLE BETWEEN THE TWO LOCATIONS.

THE PURPOSE OF THIS MODIFICATION IS TO REPLACE THE PRESENT LEASED TELEPHONE LINE COMMUNICATING SYSTEM AT STATION 13A WITH A FIBER OPTIC COMMUNICATION SYSTEM THAT WILL TIE INTO THE PRESENT MICROWAVE SYSTEM LOCATED AT STATION 13.

THIS MODIFICATION INVOLVES THE INSTALLATION OF FIBER OPTIC MULTIPLEXING AND CHANNEL BANK EQUIPMENT TO BE INSTALLED AT THE STATION 13 RADIO TOWER AND AT STATION 13A AND BE CONNECTED BY A LINK OF FIBER OPTIC CABLE BETWEEN THE TWO LOCATIONS. THIS SYSTEM WILL TIE INTO THE PRESENT MICROWAVE SYSTEM LOCATED AT STATION 13, AND WILL ALSO BE A PART OF RG&E'S OVERALL TELECOMMUNICATIONS NETWORK.

FIBER OPTIC CABLE WILL BE INSTALLED BETWEEN STATION 13A AND THE RADIO TOWER AT STATION 13. THE CABLE WILL BE INSTALLED UNDER-GROUND WITH ALL NECESSARY TRENCHING DONE OUTSIDE OF THE SECURITY FENCING AT GINNA STATION. THE OVERHEAD PART OF THE INSTALLATION WILL BE CONSTRUCTED ON AN EXISTING POLE LINE LOCATED OUTSIDE OF THE SECURITY FENCING.

THE SYSTEMS WORK ON A HOT STANDBY PRINCIPAL, IN WHICH THE FAILURE OF A SINGLE ELECTRICAL COMPONENT OR FIBER WILL NOT MAKE THE SYSTEM INOPERATIVE. TOTAL FAILURE OF THE SYSTEM WOULD HAVE THE SAME AFFECT TO STATION 13 AS TELEPHONE CABLE FAILURE WOULD HAVE ON THE STATION UNDER PRESENT CONDITIONS.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA FSAR AND THE EVENTS REQUIRING ANALYSIS BY THE USNRC REGULATORY GUIDE 1.70. THE EVENTS RELATED TO THIS MODIFICATION ARE:

(1) SEISMIC EVENT (2) LOSS OF EXTERNAL ELECTRICAL LOAD (3) LOSS OF OFFSITE A.C. POWER (4) MAJOR AND MINOR FIRES THIS MODIFICATION DOES NOT INSTALL ANY NEW OR MODIFY ANY EXISTING EQUIPMENT NECESSARY FOR THE SAFE SHUTDOWN OF THE PLANT. NEW EQUIPMENT WILL NOT BE LOCATED IN ANY AREA THAT CONTAINS SAFETY RELATED EQUIPMENT'HE MODIFICATION ISi THEREFOREi DESIGNATED AS NON-SEISMIC.

THIS MODIFICATION WILL IMPROVE AND PROVIDE REDUNDANCY IN EQUIPMENT COMMUNICATIONS TO/FROM STATION 13A. THIS MODIFICATION WILL NOT CHANGE ANY OF THE CONTROL, OR INDICATION FUNCTIONS ASSOCIATED WITH STATION 13A THEREFORE'O NEW FAILURE MODESi BEYOND THOSE ASSOCIATED WITH THE ORIGINAL CONTROL SCHEMES, WILL BE INTRODUCED BY THE MODIFICATION RELATIVE TO LOSS OF EXTERNAL ELECTRICAL LOAD OR LOSS OF OFFSITE AC POWER.

THIS MODIFICATION DOES NOT INVOLVE THE INSTALLATION OF ANY EQUIPMENT IN A GINNA FIRE AREA. AN APPENDIX R EVALUATION IS, THEREFORE, NOT REQUIRED.

IN ACCORDANCE WITH THE DESIGN CRITERIA, THE CABLE ROUTING WILL BE ENTIRELY OUTSIDE OF THE SECURITY FENCE PERIMETER. THEREFORE, NO UNDERGROUND SAFETY RELATED CIRCUITS WITHIN THE SECURITY FENCE BOUNDARY WILL BE AFFECTED.

IT HAS BEEN DETERMINED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED. IT HAS ALSO BEEN DETERMINED THAT THE ADEQUACY OF STRUCTURESi SYSTEMSi AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR - 4522 4160V AND 34.5KV BREAKER SWITCH RELOCATION THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES THE RELOCATION OF 4160V AND 34.5KV BREAKER SWITCHES ON THE MCB.

THE PROPOSED MODIFICATION WILL MINIMIZE THE POTENTIAL FOR OPERATOR ERRORi BY RELOCATING BREAKER SWITCHES ON THE MCBi SO THAT THEY ARE CONSISTENT WITH THE BREAKER CONFIGURATION ON THE 4160 VOLT BUSES.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND THE EVENTS REQUIRING ANALYSIS BY NRC REGULATORY GUIDE 1 70. THE EVENTS RELATING TO THIS MODIFICATION ARE:

1) LOSS OF OFFSITE AC POWER.

2) NATURAL EVENTS/FIRE AND EARTHQUAKE.

THE FIRST EVENT THAT HAS BEEN ANALYZED FOR THIS MODIFICATION CONCERNS THE LOSS OF OFFSITE AC POWER. THIS MODIFICATION WILL NOT CHANGE ANY ELECTRICAL CIRCUIT DESIGN OR DESIGN INTENT ASSOCIATED WITH 4160 VOLT OR 34.5KV BUSES. THEREFORE, THIS MODIFICATION WILL NOT DEGRADE THE EXISTING CAPABILITY TO DEAL WITH THE OFF-SITE AC POWER LOSS INCIDENT.

THE SECOND EVENT ANALYZED IS THE EFFECT OF A FIRE ON THE PLANT DUE TO THIS MODIFICATION. NO NEW WIRING IS ANTICIPATED, BUT IN THE EVENT ANY NEW WIRING IS REQUIRED IT SHALL MEET THE REQUIREMENTS OF IEEE STD. 383-1974 FLAME TEST. THUS THERE IS NO SIGNIFICANT INCREASE IN THE FIRE LOADING DUE TO THIS MODIFICATION.

THE THIRD EVENT ANALYZED IS THE EFFECT OF A SEISMIC EVENT ON THE PLANT DUE TO THIS MODIFICATION. THE EXISTING CONTROL SWITCHES WILL BE REAEGVQTGED WITH MINIMAL DISTURBANCE OF EXISTING WIRING'HE SEISMIC ANALYSIS PERFORMED UNDER EWR 2831 STILL APPLIES FOR THIS MODIFICATIONS THEREFORE'2 OF REGULATORY GUIDE 1 BE MET. THUS THE CONSEQUENCES OF A FAILURE DUE TO A SEISMIC

'9 WILL EVENT ARE MITIGATED.

BASED UPON THE ABOVE ANALYSIS, IT HAS BEEN DETERMINED THAT:

A) THE, MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION ARE NOT REDUCED AND B) THE STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS ARE ADEQUATE.

THE PROBABILITY OF OCCURRENCE AND THE CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY PREVIOUSLY EVALUATED IN THE SAFETY ANALYSIS REPORT ARE NOT INCREASED.

EWR-4525 OFFSZTE POWER RECONFZGURATION THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES THE IMPROVEMENT OF THE GINNA STATION OFFSITE POWER SUPPLY SYSTEM. THIS WILL INVOLVE SPLITTING THE 34.5 KV BUS INTO TWO SECTIONS WITH NO TIE BREAKER ONE BUS SECTION WILL RECEIVE POWER FROM EXISTING OFFSITE CIRCUIT 751 (STATION 204) THROUGH A 34.5 KV BREAKER AND SUPPLY STATION AUXILIARY TRANSFORMER 12A, WHILE THE OTHER SECTION IS FED BY CIRCUIT 767 (STATION 13A) TO SUPPLY STATION AUXILIARY TRANSFORMER 12B.

EACH STATION AUXILIARY TRANSFORMER WILL PROVIDE THE NORMAL FEED TO ONE 4160 VOLT SAFETY SOURCE BUS AND FUNCTION AS THE ALTERNATE FEED TO THE OTHER 4160 VOLT SAFETY SOURCE BUS. AUTOMATIC TRANSFERS WILL BE MADE BETWEEN NORMAL AND ALTERNATE SOURCES WITHOUT UNNECESSARY DIESEL STARTS.

REVISION 1 TO THIS DESIGN CRITERIA AND SAFETY ANALYSIS INCORPORATES CHANGES FROM REVISION Oi TO CORRECT TYPOGRAPHICAL ERRORS'O INCLUDE ALL MODIFICATIONS PREVIOUSLY ADDRESSED UNDER EWR 4522i TO ADD ADDITIONAL REFERENCES, CODES AND STANDARDS, TO ADD MISSING FIGURES, TO FINALIZE SECTIONS OF THE DESIGN CRITERIA AND SAFETY ANALYSIS WHICH HAD PREVIOUSLY NOT BEEN APPROVED.

NOTE PREVIOUSLY PORC APPROVAL OF REVISION 1 OF DESIGN CRITERIA AND SAFETY ANALYSIS HAD BEEN LIMITED TO THOSE SECTIONS RELATED TO THE INSTALLATION OF SWITCHGEAR AND BUS DUCT SUPPORT FOUNDATIONS AND SCREENWALL PENETRATION.

REVISION 2 TO THE DESIGN CRITERIA INCORPORATES CHANGES FROM REVISION 1, TO PROVIDE CLARIFICATION OF FIRE PROTECTION REQUIREMENTS AND TO DESCRIBE THE MEASURES TO BE TAKEN TO ENSURE THAT THE MODIFICATION WILL NOT, DEGRADE EXISTING FIRE BARRIERS OR AFFECT THE PERFORMANCE OF ANY EXISTING FIRE PROTECTION EQUIPMENT.

THE SAFETY ANALYSIS DATED 1/25/89 REVISION 2 SUPERCEDES REVISION 1 SENT OUT FOR PRE-PORC REVIEW. REVISION 2 CORRECTED TYPOGRAPHICAL ERRORS IN PARAGRAPHS 1.1.8.1, 1.1.8.2, AND 3.5 DELETED THE FIRST SENTENCE OF PARAGRAPH 3.3.1 AND CHANGED THREE SUCCESSIVE TO TWO SUCCESSIVE IN PARAGRAPH 3.4.1 REVISION 3 OF THE SAFETY ANALYSIS INCORPORATES CHANGES FROM REVISION 2 TO UPDATE THE REVISION OF THE DESIGN CRITERIA IN SECTION 2.0 REFERENCE DOCUMENTS.

REVISION 4 OF THE SAFETY ANALYSIS REPLACES SECTION 3 2.2i APPENDIX R REQUIREMENTS, TO COINCIDE WITH THE CHANGES IN DESIGN CRITERIA REVISION 2 A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND EVENTS REQUIRING ANALYSIS BY USNRC REGULATORY GUIDE 1.70 THE EVENTS RELATED TO THIS MODIFICATION ARE FIRE AND EARTHQUAKE, LOSS OF OFFSITE POWER AND LOSS OF ELECTRICAL LOAD.

FIRE AND EARTHQUAKE ARE REVIEWED AS FOLLOWS:

SECTION 27.3 OF THE DESIGN CRITERIA DETAILS CARE TO BE TAKEN WITH FIRE STOPS. NEW WIRING AND CABLE WILL BE REQUIRED FOR THIS MODIFICATION WHICH COULD ADD TO THE FIRE LOADING OF THE PLANT, AND BECAUSE OF THIS POTENTIALi THE DESIGN CRITERIA REQUIRES THAT ALL SUCH CABLE MEET THE IEEE-383-1974 FLAME TEST REQUIREMENTS.

THEREFOREi THIS MODIFICATION WILL CAUSE NO SIGNIFICANT INCREASE IN FIRE PROPAGATION HAZARD.

THIS MODIFICATION HAS BEEN REVIEWED PER ASSUMPTIONS OF APPENDIX R ALTERNATIVE SHUTDOWN SYSTEM TO ENSURE THAT FAILURE OF ANY ELECTRICAL CABLE INSTALLED AS A PART OF THIS MODIFICATION WILL NOT RESULT IN THE DISABLING OF VITAL EQUIPMENT NEEDED TO SAFELY SHUTDOWN THE PLANT DURING POSTULATED FIRES.

FAULT DUTIES RESULTING FROM THIS MODIFICATION TO THE OFFSITE POWER SYSTEM WILL NOT CAUSE THE DESIGN REQUIREMENTS OF CONTAINMENT ELECTRIC PENETRATION ASSEMBLIES AS SPECIFIED IN IEEE-317-1983 TO BE EXCEEDED.

THIS MODIFICATION IS CLASSIFIED NON-CLASS 1E CONSISTENT WITH THE CLASSIFICATION OF THE OFFSITE POWER SYSTEM. THIS CLASSIFICATION IS ACCEPTABLE BECAUSE OFFSITE POWER IS NOT NEEDED FOR SAFE SHUTDOWN.

CHANGES TO THE MCB REQUIRED BY THIS MODIFICATION ARE ACCEPTABLE BECAUSE THE DESIGN CRITERIA REQUIRES THEY NOT DEGRADE MCB SEISMIC CAPABILITY.

LOSS OF OFFSITE POWER IS REVIEWED AS FOLLOWS:

THE PURPOSE OF THIS MODIFICATION IS TO INCREASE THE INDEPENDENCE OF THE INCOMING SUPPLIES TO THE PPS WITHOUT CHANGING THE PRIORITY FOR THROWOVER SEQUENCE IN SUPPLY TO THE SAFETY BUSES. THE CONSEQUENCE OF A SINGLE CONTINGENCY (FAILURE OF A COMPONENT) IN THE PPS WILL BE AUTOMATIC TRANSFER TO A SECOND PPS CIRCUIT. THIS WILL REDUCE THE PROBABILITY FOR TRANSFER OF SAFETY RELATED LOADS TO THE EMERGENCY POWER SYSTEM THE MARGIN OF SAFETY, IN TERMS OF RELIABILITY OR NUMBER OF AUTOMATIC TRANSFERS TO ALTERNATE SUPPLIES PRIOR TO DEPENDENCE UPON DIESEL GENERATORS IS INCREASED.

THE PROBABILITY OF LOSS OF PPS IS DECREASED AND THE DESIGN ADEQUACY AS DOCUMENTED IN THE UFSAR IS ENHANCED.

BASED ON SECTION 17.2.2 OF THE DESIGN CRITERIA BOTH OFFSITE TRANSMISSION SOURCES (CIRCUIT 767 AND 751) ARE EACH REQUIRED TO HAVE ADEQUATE POWER CAPABILITIES TO SUPPLY ALL CLASS 1E AND NON-CLASS 1E PLANT LOADS. THIS IS VERIFIED BY TESTS IN SECTION 23.1 OF THE DESIGN CRITERIA. SINCE BOTH OF THE OFFSITE SOURCES EACH HAVE ADEQUATE POWER CAPABILITIES AND ORIGINATE FROM DIFFERENT SWITCHING STATIONS, THEY ARE TRULY INDEPENDENT SOURCES OF OFFSITE POWER. THEREFORE, THIS MODIFICATION WILL RESULT IN A DECREASE IN THE PROBABILITY OF LOSS OF OFFSITE POWER.

LOSS OF ELECTRICAL LOAD IS REVIEWED AS FOLLOWS:

UPON LOSS OF ELECTRICAL LOAD UNIT AUXILIARY LOADS ARE TRANSFERRED FROM THE 11 TRANSFORMER TO THE PPS. THE CONSEQUENCE OF A SINGLE CONTINGENCY IN THE PPS WILL BE AS DESCRIBED IN 3.3.1. EACH OF THE PPS SUPPLIES IS CAPABLE OF CARRYING FULL SAFETY AND UNIT AUXILIARY ELECTRICAL LOADS. THIS WILL REMAIN UNCHANGED BY THIS MODIFICATION AND AS PRESENTED IN THE UFSAR. A DOUBLE CONTINGENCY (FAILURE OF TWO PPS COMPONENTS) WILL BE REQUIRED FOR BLACKOUT OF THE PPS. THE MARGIN OF SAFETY FOR THIS EVENT IS THEREFORE, ALSO ENHANCED AS DESCRIBED IN 3.3 1. ONLY AFTER TWO SUCCESSIVE INDEPENDENT SUPPLIES BECOME UNAVAILABLE WILL CLASS 1E DEPENDENCE ON EMERGENCY DIESEL GENERATORS OCCUR.

THEREFORE, THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT WILL BE ENHANCED. THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND FOR THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED.

THE PROBABILITY OF OCCURRENCE OR THE CONSEQUENCE OF AN ACCIDENT OR MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY, PREVIOUSLY EVALUATED IN THE SAFETY ANALYSIS REPORT WILL BE REDUCED BY THE PROPOSED MODIFICATION THE POSSIBILITY OF AN ACCIDENT OR A MALFUNCTION OF A DIFFERENT TYPE THAN ANY EVALUATED PREVIOUSLY IN THE SAFETY ANALYSIS WILL NOT BE CREATED BY THE PROPOSED MODIFICATION.

THE MARGIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION WILL NOT BE REDUCED BY THE PROPOSED MODIFICATION.

EWR-4644 GSU DATA AC UISITION THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES AN EVALUATION OF THE PRESENT EQUIPMENT USED TO MONITOR THE GENERATOR STEP-UP TRANSFORMER (GSU) REVEALED AN INACCURACY OF AT LEAST 10 C. IT IS IMPORTANT TO MAINTAIN THE TEMPERATURE OF THE GSU WITHIN THE PROPER OPERATING TEMPERATURE LIMITS.

THIS MODIFICATION WILL REPLACE THE EXISTING GSU TOP OIL TEMPERATURE GAUGE AND THERMOCOUPLE COMBINATION. THE FUNCTION OF THE REPLACEMENT INSTRUMENTATION IS TO MORE ACCURATELY MONITOR THE TOP OIL TEMPERATURE OF THE GSU TRANSFORMER. THE REPLACEMENT INSTRUMENTATION WILL PROVIDE LOCAL INDICATION, ALARM CONTACT OUTPUTS AND TWO ANALOG OUTPUTS PROPORTIONAL TO THE TEMPERATURE BEING MONITORED. ONE ANALOG OUTPUT WILL BE SENT TO THE PLANT PROCESS COMPUTER SYSTEM (PPCS). THE SECOND ANALOG OUTPUT WILL NOT BE USED AT THIS TIME.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND EVENTS REQUIRING ANALYSIS BY USNRC REG. GUIDE 1.70. THE EVENTS RELATING TO THIS MODIFICATION ARE MAJOR AND MINOR FIRES AND A SEISMIC EVENT. EQUIPMENT INSTALLED UNDER THIS MODIFICATION IS NOT REQUIRED TO FUNCTION DURING OR AFTER ACCIDENT CONDITIONS.

NEW WIRING AND CABLE WHICH MAY BE REQUIRED FOR THIS MODIFICATION COULD ADD TO THE FIRE LOADING OF THE PLANT. THEREFORE, THE DESIGN CRITERIA REQUIRES THAT ALL SUCH CABLES MEET ZEEE 383-1974 FLAME TEST REQUIREMENTS. FIRE STOPS WILL BE TREATED AS IDENTIFIED IN SECTION 28.2 OF THE DESIGN CRITERIA. BECAUSE OF THIS, THERE WILL BE NO SIGNIFICANT INCREASE IN THE FIRE LOADING CAUSED BY THIS MODIFICATION.

AN APPENDIX R CONFORMANCE REVIEW SHALL BE PREPARED TO DETERMINE THAT THE PROPOSED MODIFICATION DOES NOT IMPACT APPENDIX R COMPLIANCE.

BASED ON REGULATORY GUIDE 1.29 AND CONSISTENT WITH APPENDIX A OF THE GINNA STATION QUALITY ASSURANCE MANUAL THIS MODIFICATION SHALL BE NON-SEISMIC. THIS MODIFICATION IS NOT REQUIRED FOR THE SAFE SHUTDOWN OF THE REACTOR.

WHERE APPLICABLE, THOSE PORTIONS OF THIS MODIFICATION WHOSE FAILURE COULD PRECLUDE SAFETY RELATED EQUIPMENT FROM PERFORMING THEIR SAFETY RELATED FUNCTIONS, SHALL BE RESTRAINED AND SUPPORTED IN A MANNER COMPARABLE TO SEISMIC CATEGORY I. THIS SHALL BE PERFORMED SUCH THAT SAFETY-RELATED EQUIPMENT ZS NOT PREVENTED FROM PREFORMING ITS INTENDED FUNCTION BEFORE, DURING OR AFTER A SAFE SHUTDOWN EARTHQUAKE (SSE).

IT HAS BEEN DEMONSTRATED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATION AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION HAVE NOT BEEN REDUCED. THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED.

BASED UPON A REVIEW OF THE, UFSAR AND THE REQUIREMENTS OF GINNA STATION TECHNICAL SPECIFICATIONS, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR 4756 MCB ANNUNCIATOR ALARM CRDR THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES THE REPLACEMENT OF THE MAIN CONTROL BOARD EXISTING ALARM BUZZER WITH AN ADJUSTABLE ALARM.

REVISION 2 TO THIS DESIGN CRITERIA AND SAFETY ANALYSIS ADDRESSES SETTING THE NEW CONTROL ROOM ANNUNCIATOR ALARM AT LEAST 5 dBA ABOVE BACKGROUND WITH THE OTHER MCB ALARMS WITHIN A BAND OF +/-

2.5 dBA AROUND THE ANNUNCIATOR LEVEL.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND THE EVENTS REQUIRING ANALYSIS BY RGE(E ENGINEERING PROCEDURE QE311 SECTION 3.2.2. THE EVENTS RELATED TO THIS MODIFICATION ARE:

1) SEISMIC EVENT

2) FIRES THIS MODIFICATION DOES NOT INSTALL ANY NEW OR MODIFY ANY EXISTING EQUIPMENT NECESSARY FOR THE SAFE SHUTDOWN OF THE PLANT AS IDENTIFIED IN THE APPENDIX R SUBMITTAL.

ANY PORTION OF THIS MODIFICATION INVOLVING THE MAIN CONTROL BOARD IS DESIGNATED SEISMIC CATEGORY I. THE REMAINING WORK FOR THIS MODIFICATION WILL BE DESIGNED TO MEET THE REQUIREMENTS OF USNRC REGULATORY GUIDE 1.29, POSITION C.2 THIS MODIFICATION INVOLVES THE INSTALLATION OF EQUIPMENT AND CABLE IN THE CONTROL BUILDING, FIRE AREA CC ZONE CR. A REVIEW WILL BE PERFORMED TO ASSURE CONTINUED COMPLIANCE WITH 10 CFR 50, APPENDIX R ALL NEW WIRING WILL BE QUALIFIED TO IEEE 383-1974 FLAME TEST REQUIREMENTS.

FIRE BARRIER PENETRATIONS WILL BE REPAIRED OR REPLACED IN ACCORDANCE WITH EXISTING PLANT PROCEDURES. THEREFORE EXISTING SEALS WILL NOT BE DEGRADED..

THIS MODIFICATION DOES NOT AFFECT THE SAFE SHUTDOWN ANALYSIS IN THE APPENDIX R SUBMITTAL FOR THE FOLLOWING REASONS:

A) THE MODIFICATION INVOLVES EQUIPMENT WHICH IS NOT IDENTIFIED AS SAFE SHUTDOWN EQUIPMENT IN THE APPENDIX R SUBMITTAL.

B) THERE IS NO EFFECT ON SEPARATION OF EXISTING CIRCUITS/

ASSOCIATED CIRCUITS, OR FIRE AREA BOUNDARIES AS ANALYZED IN THE APPENDIX R SUBMITTAL.

THIS MODIFICATION WILL NOT AFFECT THE CAPABILITIES OF THE ALTERNATIVE SHUTDOWN SYSTEM. FURTHERMOREi NONE OF THE EXISTING PROCEDURES FOR OBTAINING AN ALTERNATIVE SAFE SHUTDOWN WILL BE I

EFFECT VE ~ I II I I I TH S MOD F CAT ON i THEREFORE i COMPL ES W TH 1 0 CFR 50 i APPENDIX R BASED UPON A REVIEW OF THE UFSAR AND THE REQUIREMENTS OF GINNA STATION TECHNICAL SPECIFICATIONS, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURESi SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR-4759 HIGH MAST LIGHTING CABLE REPLACEMENT THIS EWR (ENGINEERING WORK REQUEST) ADDRESSES THE MODIFICATION TO REMOVE ANTIFALL DEVICES AND THE REPLACEMENT OF THE LIGHT FIXTURE LIFTING CABLES ON LIGHTING POLES g1i 3i 4i 5i 6 AND 7 ~

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND THE EVENTS REQUIRING ANALYSIS BY NRC REGULATORY GUIDE 1.70. EVENTS RELATED TO THIS MODIFICATION: (1) LOSS OF ALL I I EXTERNAL ( OFFS TE) AC POWER TO THE STAT ON i ( 2 ) I NTERNAL AND I

EXTERNAL EVENTS/ F RE i FLOOD i STORM i OR EARTHQUAKE THE FIRST EVENT CONSIDERED IS "LOSS OF ALL EXTERNAL (OFFSITE) AC POWER TO THE STATION". THE MOTOR DRIVEN LIFT MECHANISMS ARE FED FROM NON-1E SAFETY RELATED BUSSES. SINCE THERE IS NO CHANGE TO THE 1E SAFETY RELATED BUSSES, THE PROBABILITY OF A LOSS OF AC POWER HAS NOT BEEN INCREASED.

I THE SECOND EVENT CONSIDERED S INTERNAL AND EXTERNAL EVENTS/ FIRE i FLOODS STORMED OR EARTHQUAKE I THIS MODIFICATION S NOT REQUIRED TO BE 1E NOR SEISMIC. THE FAILURE OF THE LIFT MECHANISM WILL NOT AFFECT SAFETY RELATED EQUIPMENT. THIS MODIFICATION IS OUTSIDE THE PERIMETER OF ANY FIRE AREAS. THERE IS NO IMPACT ON APPENDIX R OR OTHER FIRE PROTECTION REQUIREMENTS AND NO ADDITIONALAPPENDIX R REVIEW IS REQUIRED.

BASED UPON THE ABOVE ANALYSIS, IT HAS BEEN DETERMINED THAT:

A) THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION ARE NOT REDUCED AND B) THE STRUCTURES i SYSTEMS i AND COMPONENTS PROVI DED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS ARE ADEQUATE.

THE PROBABILITY OF OCCURRENCE AND THE CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY PREVIOUSLY EVALUATED ZN THE SAFETY ANALYSIS REPORT ARE NOT INCREASED.

EWR 4809 DIESEL FIRE PUMP BATTERY CHARGER THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES THE REPLACEMENT OF THE BATTERY CHARGER FOR THE DIESEL FIRE PUMP. THE DESIGN OF THE EXISTING CHARGER IS THAT THROUGH A TIMING CAM, THE A AND B BATTERIES'OR STARTING THE DIESEL FIRE PUMPS ARE ALTERNATELY CHARGED FOR ABOUT TWO MINUTES EVERY OTHER HOUR. THE NEW BATTERY CHARGER CONTINUOUSLY FLOAT CHARGES THE BATTERIES. IT WOULD HAVE THE CAPABILITY TO EQUALIZE OR RECHARGE THE BATTERIES AND AFTER THE REQUIRED CHARGE PERIOD RETURN TO THE FLOAT LEVEL AUTOMATICALLY.

THIS WOULD PROVIDE BETTER CONTROL AND PROLONG BATTERY LIFE.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA UFSAR AND THE EVENTS REQUIRING ANALYSIS BY NRC REGULATORY GUIDE 1.70.

THE EVENTS RELATED TO THIS MODIFICATION ARE AS FOLLOWS:

1) SEISMIC EVENT

2) FIRE IN THE PLANT THE FIRST EVENT ANALYZED IS THE EFFECT OF A SEISMIC EVENT. THE DESIGN CRITERIA REQUIRES THE NEW BATTERY CHARGER TO BE SEISMICALLY MOUNTED TO CATEGORY 1 CRITERIA. THEREFORE, THE MODIFICATION WILL NOT ADVERSELY AFFECT THE SYSTEM DURING A SEISMIC EVENT.

THE SECOND EVENT ANALYZED IS THE EFFECT OF A FIRE IN THE PLANT DUE TO THIS MODIFICATION. THE CONTROL WIRING USED FOR THIS MODIFICATION IS REQUIRED TO MEET THE REQUIREMENTS OF IEEE STANDARD 383-1974, FLAME TEST SPECIFICATION.

BASED UPON A REVIEW OF THE UFSAR, AND THE REQUIREMENTS OF THE GINNA STATION TECHNICAL SPECIFICATIONS, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED. IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR-4931 TDAFWP CHECK VALVE REPLACEMENT THIS EWR (ENGINEERING WORK REQUEST) ADDRESSES THE REPLACEMENT OF VALVES 4003 AND 4004, EVALUATION OF THE EFFECTS OF VALVE REPLACEMENTS AND THE ADDITION/MODIFICATION OF PIPE SUPPORT(S) IF DEEMED NECESSARY.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND THE EVENTS REQUIRING ANALYSIS BY USNRC REG.

GUIDE 1.70. EVENTS RELATED TO THIS ANALYSIS ARE:

A) FIRES B) SEISMIC EVENTS C) PIPE BREAKS OUTSIDE THE CONTAINMENT BUILDING D) PIPE BREAKS INSIDE THE CONTAINMENT BUILDING E) ,LOSS OF COOLANT ACCIDENT F) LOSS OF ALL A.C. POWER G) COOLDOWN H) STEAM GENERATOR TUBE RUPTURE I) LOSS OF MAIN FEEDWATER THIS MODIFICATION WILL NOT CAUSE THE DEGRADATION OF EXISTING FIRE BARRIERS. MATERIALS USED WILL MEET CRITERIA EQUAL TO OR GREATER THAN THOSE PRESENTLY INSTALLED. FURTHERMORE, THIS MODIFICATION WILL BE REVIEWED AGAINST THE ASSUMPTIONS OF 10CFR50 APPENDIX R TO ASSURE THAT ALL EXISTING FIRE PROTECTION FEATURES REQUIRED TO COMPLY WITH AND MAINTAIN EQUIVALENT LEVELS OF PROTECTION WILL BE MET DURING AND FOLLOWING THE MODIFICATION.

ALL PIPING AND ANY PIPE SUPPORT MODIFICATIONS WILL BE EVALUATED, IN REGARD TO A SEISMIC EVENT, TO CRITERIA IDENTICAL TO THE EWR 2512 SEISMIC UPGRADE PROGRAM SO AS TO EQUAL OR IMPROVE THE SYSTEMS CAPABILITY TO WITHSTAND A SEISMIC EVENT.

REPLACEMENT OF THE EXISTING CHECK VALVES IN THE AUXILIARY FEEDWATER SYSTEM WILL NOT ADVERSELY AFFECT AUXILIARY FEEDWATER PERFORMANCE IN RESPONSE TO PIPE BREAKS'OCAL STEAM GENERATOR TUBE RUPTURE AND LOSS OF MAIN FEEDWATER. PREVIOUS PIPE BREAK REQUIREMENTS WILL NOT BE AFFECTED, AS THE SYSTEM WILL BE HYDROSTATICALLY TESTED TO PROVE INTEGRITY PRIOR TO TURNOVER FOR USE.

ALL ACCIDENTS LISTED (E THROUGH I ABOVE) ARE NOT ADVERSELY AFFECTED. THE REDUCTION IN LEAKAGE BETWEEN STEAM GENERATORS (UNDER THIS MODIFICATION) WILL IN FACT REDUCE THE IMPACT OF THESE EVENTS THUS, THIS MODIFICATION NEITHER INCREASES THE CONSEQUENCES, NOR DOES ZT REDUCE THE MARGINS OF SAFETY FOR, 1) EQUIPMENT REQUIRED TO FUNCTION DURING AND FOLLOWING A SEISMIC EVENT, 2) AFFECT THE LEVELS OF PROTECTION FROM FIRES DURING AND FOLLOWING MODIFICATIONS TO THE TDAFWP PIPING SYSTEM, 3) ALTER THE PERFORMANCE OF THE SYSTEM IN RESPONSE TO PIPE BREAKS INSIDE AND OUTSIDE CONTAINMENT, INCLUDING LOCA Sg LOSS OF MAIN FEEDWATERg COOLDOWN AND STEAM GENERATOR TUBE RUPTURE, AND 4) THE REPLACEMENT OF THE TDAFWP DISCHARGE CHECK VALVES WILL NOT BE AFFECTED BY LOSS OF ALL A.C.

POWER DUE TO THEIR PASSIVE DESIGN FEATURES.

BASED UPON A REVIEW OF THE UFSAR AND TECHNICAL SPECIFICATIONS, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED. IT HAS ALSO BEEN CONCLUDED THAT ADEQUACY OF STRUCTURES'YSTEMS'ND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR-5025 MCB KEY SWITCHES CONTROL THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES LER 89-016, WHICH IDENTIFIED A POTENTIAL COMMON MODE FAILURE DUE TO AN OT-2 CONTACT BLOCK PLUNGER MECHANISM MALFUNCTION. A SINGLE OT-2 SWITCH ON THE MCB IS USED TO CONTROL THE SAFETY INJECTION BLOCK/NORMAL/UNBLOCK FUNCTION FOR BOTH TRAINS OF SAFETY INJECTION (SI) A MALFUNCTION COULD RESULT IN THE BLOCKING OF SOME AUTOMATIC ACTUATION FEATURES OF SI ~ TO CORRECT THE DEFICIENCY'HE PRESENT SI BLOCK FUNCTION WILL BE MODIFIED TO PROVIDE A SEPARATE BLOCK/NORMAL/UNBLOCK SWITCH FOR EACH TRAIN.

A REVIEW WAS PERFORMED TO IDENTIFY ANY ADDITIONAL FUNCTIONS SUBJECT TO A SIMILAR COMMON MODE FAILURE. THE RESULTS CONCLUDED I I THAT THE S RESET g CONTAINMENT SPRAY RESET g CONTAINMENT SOLATION RESET AND CONTAINMENT VENTILATION ISOLATION RESET SWITCHES HAVE SIMILAR DESIGN DEFICIENCIES. TO CORRECT THE DEFICIENCIES AND PROVIDE A SEPARATION OF TRAINS, THE WIRING OF THE SWITCHES WILL BE RECONFIGURED.

IN ADDITION, THE GARD COMMITTEE HAS RECOMMENDED THAT THE KEY PUSHBUTTONS FOR CONTAINMENT ISOLATION RESET AND CONTAINMENT VENTILATION ISOLATION RESET BE REPLACED WITH NON-KEY PUSHBUTTONS.

AS A RESULT OF THESE CHANGES AND THE GARD COMMITTEE '

RECOMMENDATION, CONGESTED AREAS OF THE LEFT FRONT SECTION WILL BE REARRANGED TO PROVIDE BETTER SEPARATION OF FUNCTIONS AND UTILIZATION OF MCB SPACE. THE DEVICES TO BE RELOCATED ARE THE EXISTING SI BLOCK/NORMAL/UNBLOCK/ AMSAC SYSTEM RESETS BOTH MANUAL CONTAINMENT SPRAY VENT ISOLATION, DIESEL GENERATOR A START/

DIESEL GENERATOR B STARTS BAST LO LO LOCKOUT RESETS MANUAL SI~

MANUAL CONTAINMENT ISOLATION AND REACTOR EMERGENCY TRIP. ALSO, THE LEFT FRONT SECTION OF THE MAIN CONTROL BOARD (MCB) WILL BE RKQGVQlGED TO PROVIDE A CONSISTENT PHYSICAL RELATIONSHIP BETWEEN VALVES THAT HAVE BOTH KEY AND CONTROL SWITCHES. THE VALVES ARE:

MOV 852Ag MOV 852Bg MOV 896Ag MOV 896Bg AND MOV 856 IN ORDER TO PROVIDE THE SPACE ON THE MCB, THE CONTAINMENT SPRAY CHARCOAL FILTER DOUSE MOTOR OPERATED VALVE CONTROLS WILL BE RELOCATED TO BLANK AREA ON THE LEFT FRONT BENCHBOARD. THEY ARE: MOV-875Ag MOV 875BJ MOV 876Ag AND MOV 876B ~

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND THE EVENTS REQUIRING ANALYSIS BY NRC REGULATORY GUIDE 1.70. THE EVENTS RELATING TO THIS MODIFICATION ARE SEISMIC, FIREg AND LOSS OF POWER THE FIRST EVENT ANALYZED IS THE EFFECT OF A SEISMIC EVENT ON THE PLANT DUE TO THIS MODIFICATION. THE NEW SAFETY INJECTION (SI)

BLOCK/NORMAL/UNBLOCK SELECTOR SWITCH AND ANY REPLACED DEVICES WILL BE QUALIFIED TO MEET THE STANDARDS SET FORTH BY IEEE STD.

344-1975. THEREFORE, THE CONSEQUENCES OF A FAILURE DUE TO A SEISMIC EVENT WILL BE MITIGATED.

THE SECOND EVENT ANALYZED IS THE EFFECT OF A FIRE ON THE PLANT DUE TO THIS MODIFICATION. THE REPLACED OR ADDITIONAL AMOUNT OF CONTROL WIRING NECESSARY FOR THIS MODIFICATION IS MINIMAL AND WILL BE REQUIRED TO MEET IEEE STD. 383-1974, VERTICAL FLAME TEST REQUIREMENTS. THE ADDITIONAL FIRE LOADING IS INSIGNIFICANT; THUS, THE LIKELIHOOD OR THE SEVERITY OF FIRE RESULTING WILL NOT INCREASED.

THE THIRD EVENT ANALYZED IS THE EFFECT OF LOSS OF POWER TO THE SYSTEMS.

THE RISK OF LOSING POWER WILL NOT BE INCREASED BY THIS MODIFICATION SINCE THE ADDITIONAL SI BLOCK/MANUAL/UNBLOCK SWITCH WILL BE INSTALLED TO PROVIDE A SEPARATION OF TRAINS AND WILL OPERATE IN THE SAME MANNER UNDER VARIOUS PLANT CONDITIONS AS THE ORIGINAL CONFIGURATION. THE UFSAR SECTION REVIEWED WAS 7.1.2.

TO PROVIDE BETTER SEPARAT ION OF TRAINS J THE S I RESET g CONTAINMENT SPRAY RESET g CONTAINMENT ISOLATION RESET ~ AND CONTAINMENT VENTILATION ISOLATION RESET PUSHBUTTONS WILL BE REWIRED TO ESTABLISH INDIVIDUAL SWITCH SECTIONS SUPPLYING SIGNAL TO EACH TRAIN. THESE RESET SIGNALS DO NOT AUTOMATICALLY START SYSTEMS.

THE INITIATION OF A SYSTEM IS A SEPARATE OPERATION. MANUAL OPERATION OF EACH SYSTEM IS ALWAYS AVAILABLE. REPLACING THE CONTAINMENT ISOLATION RESET AND THE CONTAINMENT VENTILATION ISOLATION RESET KEY PUSHBUTTONS WITH NON-KEY PUSHBUTTONS WILL REQUIRE A CHANGE TO THE UFSAR SECTION 6.2.4.4.3. THE ORIGINAL CONTROL CONFIGURATION OF THE CONTAINMENT ISOLATION AND CONTAINMENT VENTILATION ISOLATION RESETS LOCKED OUT SOME AUTOMATIC ACTUATION SIGNALS ONCE THEY WERE RESET. EWR 2950 CORRECTED THAT DEFICIENCY BY REMOVING THE LOCKOUT RELAY. PRESENTLY THE SYSTEMS CANNOT BE RESET UNTIL THE INITIATING SIGNAL HAS CLEARED MAKING THE PROCEDURE TO HAVE A KEY TO RESET THEM OBSOLETE. ADDITIONAL UFSAR SECTIONS REVIEWED WERE 6 ~ 2 ~ 4 ~ 4 ~ 2g TABLE 7.3-1.

6 ~ 2 ~ 4 ~ 4 ~ 4g 7 ' ' '~ 7 ' ' 'g 9 ' '2 AND

SINCE THERE WILL BE NO CHANGE TO THE CONTROL OR MODES OF OPERATION FOR MOV 852Ag MOV 852Bi MOV 875Ag MOV 875Bi MOV 876Ag MOV 876Bg MOV<<896A, MOV-896B, AMSAC SYSTEM RESET, BOTH MANUAL CONTAINMENT SPRAY VENT ISOLATION, DIESEL GENERATOR A START, DIESEL GENERATOR B STARTi BAST LO LO LOCKOUT RESETS MANUAL SIg MANUAL CONTAINMENT ISOLATION AND REACTOR EMERGENCY TRIP THERE WILL BE NO INCREASED RISK DUE TO A LOSS OF POWER.

ITEMS ABOVE ENSURE THAT THIS MODIFICATION DOES NOT DEGRADE THE CAPABILITY OF ANY SAFETY SYSTEM TO PERFORM ITS FUNCTION. THE ASSUMPTIONS AND CONCLUSIONS OF EXISTING ANALYSES ARE UNCHANGED.

NO NEW TYPES OF EVENTS ARE POSTULATED.

THEREFORE, IT HAS BEEN DETERMINED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION HAVE NOT BEEN AFFECTED. IT HAS ALSO BEEN DETERMINED THAT THE ADEQUACYi OF STRUCTURES@ SYSTEMSi AND COMPONENTS PROVIDED FOR THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED.

.BASED UPON A REVIEW OF THE UFSAR AND THE REQUIREMENTS OF GINNA STATION TECHNICAL SPECIFICATIONS, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR-5156 PRESSURIZER INSULATION THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES THE REMOVAL OF EXISTING PRESSURIZER INSULATION AND REPLACEMENT WITH REMOVABLE TYPE REFLECTIVE INSULATION TO FACILITATE VISUAL EXAMINATION OF THE PRESSURIZER WELDS.

THE DESIGN CRITERIA AND SAFETY ANALYSIS WAS REVISED TO INCORPORATE PLANT COMMENTS, FOR REVISION 0 AND THE FOLLOWING ADDITIONAL CHANGES:

SECTION 1.3 3 OF DESIGN CRITERIA ADDED REFERENCE TO TECH. SPEC. SECTION 3.1.1.5 REQUIREMENT OF 100 KW MIN.

HEATER CAPACITY FOR OPERATION ABOVE 350 F.

SECTION 2.10.4 ADDED WORKSHEET SCA-2 TO REFERENCES.

SECTION 5.2 OF DESIGN CRITERIA CLASSIFIED ELECTRICAL CONNECTIONS TO PRESSURIZER HEATERS AS SAFETY SIGNIFICANT.

SECTION 15.2 WAS ADDED TO THE DESIGN CRITERIA HYDRAULIC REQUIREMENTS AS FOLLOWS:

15.2 THE DESIGN OF THE INSULATION SHOULD CONSIDER CLOGGING OF CONTAINMENT SUMP WHICH SHOULD NOT BE BLOCKED BY DEBRIS OF XNSULATION FOLLOWING A LOSS-OF-COOLANT ACCIDENT.

SECTION 17.0 WAS CHANGED FROM N/A TO THE FOLLOWING:

ELECTRICAL RE UIREMENTS PRESSURIZER HEATER ELECTRICAL CONNECTIONS SHALL NOT BE DEGRADED BY THIS MODIFICATION.

NON-FUNCTIONAL PRESSURIZER HEATERS SHALL BE CONSIDERED FOR RESTORATION TO SERVICE IN ACCORDANCE WITH UFSAR REQUIREMENTS.

SECTION 3.1 OF SAFETY ANALYSIS ADDED LOCA TO THE DESIGN BASIS EVENTS ASSOCIATED WITH THIS WORK.

SECTION 3.2 3 OF THE SAFETY ANALYSIS ADDED AS FOLLOWS:

3.2.3 THE EFFECTS OF LOCA HAVE BEEN ADDRESSED XN SECTION 15.2 OF THE DESIGN CRITERIA. AS DESCRIBED IN THE DESIGN CRITERIA THE INSULATION SHALL BE DESIGNED SUCH THAT THE CONTAINMENT SUMP WILL NOT BE CLOGGED BY DEBRIS OF INSULATION FOLLOWING A LOCA EVENT A REVIEW HAS BEEN MADE OF THE DESIGN BASIS EVENTS TO DETERMINE THOSE RELATED TO THE MODIFICATION. THE EVENTS ASSOCIATED WITH THIS WORK ARE:

1) FIRES

2) SEISMIC EVENTS

3) LOCA THE MODIFICATION WILL NOT INCREASE THE PROBABILITY OF THE EFFECTS OF FIRE SINCE EXISTING FIRE BARRIERS WILL NOT BE DEGRADED AND THE MATERIALS USED IN THE MODIFICATION SHALL NOT INCREASE THE PROBABILITY OR CONSEQUENCE OF A FIRE AND WILL NOT AFFECT THE PERFORMANCE OF ANY EXISTING FIRE PROTECTION EQUIPMENT. IN ADDITIONS THE MODIFICATION WILL BE REVIEWED AGAINST THE ASSUMPTIONS OF 10CFR50 APPENDIX R. DEVIATIONS WILL BE ANALYZED TO ASSURE CONTINUED COMPLIANCE WITH APPENDIX R THEREFORE i I I THE MODIFI CATIONS WILL NOT S GNI F CANTLY ALTER THE AREA FIRE LOADINGi THE SOURCES OF FIRE INITIATION'OR THE ACCEPTABILITY OF THE CONSEQUENCES OF A FIRE.

THE MODIFICATION WILL NOT ADVERSELY AFFECT THE SEISMIC QUALIFI CATION OF THE PRESSURI ZERO ITS ASSOCIATED P IP ING i OR THE REACTOR COOLANT SYSTEM. SINCE THE INSULATION ASSEMBLY SHALL BE DESIGNED TO WITHSTAND DYNAMIC EFFECTS AND ACCELERATIONS DUE TO SEISMIC AND SYSTEM OPERATIONAL TRANSIENTS. THIS SHALL INCLUDE A REVIEW OF THE EXISTING PIPING ANALYSIS AND ASSOCIATED SUPPORTS FOR ANY EFFECTS THAT THE CHANGE IN INSULATION WEIGHT MAY HAVE ON THE ANALYSIS.

THE MODIFICATION WILL NOT ADVERSELY AFFECT THE EFFECTS OF LOCA BECAUSE THE INSULATION SHALL BE DESIGNED SUCH THAT THE CONTAINMENT SUMP WILL NOT BE CLOGGED BY DEBRIS OF INSULATION FOLLOWING A LOCA EVENT.

BASED ON THE ABOVE ANALYSIS:

1) THE MARGINS OF SAFETY DURING NORMAL OPERATION AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION ARE NOT REDUCED DUE TO THIS MODIFICATION.

2) THE STRUCTURES g SYSTEMS i AND COMPONENTS PROVI DED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS CONTINUE TO REMAIN ADEQUATE.

BASED UPON A REVIEW OF THE UFSAR AND THE REQUIREMENTS OF GINNA STATION TECHNICAL SPECIFICATIONS, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR-5162 INSTALL BALANCED MAGNETIC SWITCHES THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES THE INSTALLATION OF BALANCED MAGNETIC SWITCHES (BMS) ON DOORS S54 AND S55.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA UFSAR AND THE EVENTS REQUIRING ANALYSIS BY THE USNRC REGULATORY GUIDE 1.70. THE EVENTS RELATED TO THIS MODIFICATION ARE:

1) SEISMIC EVENT

2) MAJOR AND MINOR FIRES

3) INDUSTRIAL SECURITY THIS MODIFICATION DOES NOT INSTALL ANY NEW OR MODIFY ANY EXISTING EQUIPMENT NECESSARY FOR THE SAFE SHUTDOWN OF THE PLANT. NEW EQUIPMENT WILL NOT BE LOCATED IN ANY AREA THAT CONTAINS SAFETY RELATED EQUIPMENT THE MODIFICATION ISi THEREFORE'ESIGNED AS NON-SEISMIC.

THIS MODIFICATION INVOLVES THE INSTALLATION OF EQUIPMENT IN A I I G NNA F RE AREA I AN APPEND X R EVALUAT ON I ISi THEREFORE i REQUIRED.

THE INSTALLATION OF ADDITIONAL BMS DOES NOT EFFECT SECURITY OPERATIONS AND PROVIDES GREATER PROTECTION TO THE VITAL AREA.

ITEMS ABOVE ENSURE THAT THIS MODIFICATION DOES NOT DEGRADE THE CAPABILITY OF ANY SAFETY SYSTEM TO PERFORM ITS FUNCTION. THE ASSUMPTIONS AND CONCLUSIONS OF EXISTING ANALYSES ARE UNCHANGED.

NO NEW TYPES OF EVENTS ARE POSTULATED.

THEREFORE, IT HAS BEEN DETERMINED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION HAVE NOT BEEN AFFECTED. IT HAS ALSO BEEN DETERMINED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED.

BASED UPON A REVIEW OF THE UFSAR AND THE REQUIREMENTS OF GINNA STATION TECHNICAL SPECIFICATIONS, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

EWR-5340 GENERATOR STEP-UP TRANSFORMER MODIFICATIONS THIS ENGINEERING WORK REQUEST (EWR) ADDRESSES THE COOLERS ON THE GENERATOR STEP-UP TRANSFORMER (GSU) AT GINNA WHICH ARE OIL TO AIR HEAT EXCHANGERS DESIGNED TO REMOVE HEAT FROM THE INTERIOR OF THE TRANSFORMER. HEAT IS GENERATED BY CORE AND WINDING MATERIALS USED FOR CONSTRUCTION OF THE TRANSFORMER. THERE ARE ELEVEN (11)

COOLERS ON THE TRANSFORMER WITH EACH COOLER CONSISTING OF THREE (3) FANS AND ONE (1) OIL PUMP. THE FANS AND PUMPS ARE DRIVEN BY 440 VOLT, 3 PHASE ELECTRIC MOTORS. THE INSULATION ON THE WIRING SUPPLYING POWER TO THESE FANS AND PUMPS HAS DETERIORATED AND WILL BE REPLACED WITH NEW WIRING. DETERIORATION OF THE INSULATION HAS BEEN CAUSED BY HEAT GENERATED BY THE GSU.

A STUDY HAS INDICATED THAT CIRCUIT BREAKERS FOR PROTECTION OF COOLER MOTORS AND SUPPLY SOURCES TO THE COOLER GROUPS WILL OPERATE SIMULTANEOUSLY FOR A FAULT ON A SINGLE COOLER MOTOR.

THIS ACTION RESULTS IN LOSS OF POWER TO 504 OF THE COOLERS ON THE GSU. CIRCUIT BREAKERS PROVIDING PROTECTION FOR EACH COOLER AND CIRCUIT BREAKERS PROVIDING PROTECTION FOR 5 AND 6 COOLER GROUPS WILL BE REPLACED WITH PROTECTIVE EQUIPMENT THAT WILL PROVIDE THE PROPER COORDINATION.

INSPECTION OF WIRING USED TO EXTEND CURRENT TRANSFORMER SECONDARY WIRING TO THE CONTROL CABINET HAS REVEALED DETERIORATION OF THE INSULATION FOR THIS WIRING. THIS WIRING LOCATED IN A RACEWAY BETWEEN THE CONTROL CABINET AND CURRENT TRANSFORMER JUNCTION BOX, WILL BE REPLACED WITH NEW WIRING. DETERIORATION OF THE INSULATION HAS BEEN CAUSED BY HEAT GENERATED BY THE GSU.

A REVIEW HAS BEEN MADE OF EVENTS ANALYZED IN THE GINNA STATION UFSAR, CHAPTER 8.0 ELECTRICALi CHAPTER 3.0 DESIGN OF STRUCTURES g I SECT ON 3 ~ 1 AND CHAPTER 9 I AUX LIARY SYSTEMS g SECTION 9.5.1 FIRE PROTECTION SYSTEMS. THE EVENTS RELATED TO I II TH S 'MOD F CATION ARE LOSS OF EXTERNAL ELECTRI CAL LOAD i LOSS OF OFFS ITE POWERS FIRES i AND SEISMI C EVENTS ~

LOSS OF OFFSITE POWER IS REVIEWED AS FOLLOWS:

WORK ON CIRCUITS 751 AND 767, BOTH SOURCES OF OFFSITE POWER, WILL NOT BE REQUIRED AS PART OF THIS MODIFICATION. IN ADDITION, WORK ON TRANSFORMERS 12A AND 12B WILL NOT BE REQUIRED AS PART OF THIS MODIFICATION.

THE WORK ON THE GSU COOLERS WILL BE SCHEDULED AROUND OUTAGES OF THE DIESEL GENERATORS AT GINNA. THE GSU IS A BACKUP SOURCE OF POWER FOR THE DIESEL GENERATORS.

THIS MODIFICATION WILL 'NOT INCREASE THE PROBABILITY OF LOSS OF OFFSITE POWER.

LOSS OF EXTERNAL ELECTRICAL LOAD EVENTS ARE REVIEWED AS FOLLOWS:

THIS MODIFICATION WILL BE PERFORMED DURING THE 1991 GINNA REFUELING OUTAGE WHEN GINNA IS OFF-LINE.

THIS MODIFICATION, AFTER COMPLETION, WILL NOT INCREASE THE PROBABILITY OF A LOSS OF EXTERNAL ELECTRICAL LOAD.

SEISMIC EVENTS ARE REVIEWED AS FOLLOWS:

THE GSU IS NOT NEEDED FOR SAFE SHUTDOWN DURING OR AFTER A SEISMIC EVENT.

FIRES ARE REVIEWED AS FOLLOWS:

THIS MODIFICATION DOES NOT INVOLVE WIRING ASSOCIATED WITH THE GSU FIRE PROTECTION SYSTEM OR FIRE BARRIERS. AN APPENDIX R CONFORMANCE VERIFICATION WILL BE PERFORMED TO DEMONSTRATE CONTINUED COMPLIANCE WITH APPENDIX R REQUIREMENTS. THEREFORE, THIS MODIFICATION HAS NO EFFECT ON FIRES AT GINNA.

THEREFORE, THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE STATION HAVE NOT BEEN AFFECTED. IT HAS ALSO BEEN DETERMINED THAT THE ADEQUACY OF STRUCTURES i SYSTEMS i AND COMPONENTS PROVI DED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED.

BASED UPON A REVIEW OF THE UFSAR AND THE REQUIREMENTS OF GINNA STATION TECHNICAL SPECIFICATIONS, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION TSR 90-186 SPRINKLER HEAD HEAT COLLECTOR INSTALLATION THIS TECHNICAL STAFF REQUEST (TSR) ADDRESSES THE ADDITION OF HEAT COLLECTORS TO SHIELD THE SPRINKLER HEADS LOCATED IN THE AREA OF THE GRATING AROUND THE CONDENSATE STORAGE TANKS IN THE SERVICE BUILDING.

THE FUNCTION OF THE HEAT COLLECTORS IS TO SHIELD THE SPRINKLER HEADS FROM POSSIBLE SOURCES OF COOLING FROM ABOVE THE GRATING.

THE HEAT COLLECTORS WILL ACT TO TRAP HEAT IN THE INSTANCE OF A FIRE AND WILL CAUSE THE SPRINKLER TO CONTINUE TO DISCHARGE EFFECTIVELY IN THE EVENT OF A FIRE.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE UFSAR AND IN TABLES 1 AND 2 OF PROCEDURE A-303 AS WELL AS THOSE REQUIRING ANALYSIS BY USNRC REG. GUIDE 1.70. THE EVENT RELATED TO THIS MODIFICATION IS A FIRE.

THIS MODIFICATION WILL NOT ALTER ASSUMPTIONS IN ANY SAFETY ANALYSIS IN THE UFSAR AND ITS SUPPLEMENTS AND WILL NOT ADVERSELY AFFECT THE WAY IN WHICH THE FIRE PROTECTION SYSTEM FUNCTIONS. IT WILL PROVIDE A MEANS TO ENSURE THAT THE APPLICABLE SPRINKLER HEADS WILL OPERATE IN THE MANNER ORIGINALLY DESIGNED FOR.

THE PROBABILITY OF OCCURRENCE OF A FIRE IN THIS AREA WILL NOT BE AFFECTED BY THIS MODIFICATION BECAUSE THE FUNCTION OF THE FIRE PROTECTION SYSTEM WILL NOT BE ALTERED AS THE MODIFICATION INCORPORATES NO COMBUSTIBLE MATERIALS.

ANY CONSEQUENCES OF A FIRE WILL REMAIN THE SAME AND THIS MODIFICATION WILL HAVE NO ADDITIONAL EFFECT ON THOSE CONSEQUENCES.

ALL EXISTING FIRE PROTECTION FEATURES REQUIRED TO ASSURE COMPLIANCE WITH 10CFR50i APPENDIX Ri OR TO MAINTAIN EQUIVALENT LEVELS OF PROTECTION FROM FIRES WILL NOT BE ALTERED DURING AND FOLLOWING IMPLEMENTATION OF THIS MODIFICATION.

THUS, THIS MODIFICATION NEITHER INCREASES THE CONSEQUENCES, NOR DOES IT REDUCE THE MARGINS OF SAFETY FOR FIRE PROTECTION FEATURES.

THE INSTALLATION OF HEAT COLLECTORS IS AN INSIGNIFICANT ADDITION TO AN EXISTING SYSTEM THAT WILL IMPROVE THE ABILITY OF THE SYSTEM TO FUNCTION PROPERLY.

BASED UPON A REVIEW OF THE UFSAR AND THE REQUXREMENTS OF GINNA STATION TECHNICAL SPECIFICATIONS, IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS, AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

TSR 90-256 INSTRUMENT AIR ISOLATION VALVE ADDITION THXS TSR (TECHNICAL STAFF REQUEST) ADDRESSES MODIFICATION OF THE EXISTING INSTRUMENT AIR LINE BY INSTALLING A MANUAL VALVE WHICH WILL PROVIDE ISOLATION CAPABILITY TO EACH TURBINE BUILDING HEADER. XN ADDITION, FITTINGS WILL BE ADDED TO ALLOW THE WORK AREA TO BE JUMPERED DURING INSTALLATION SO THAT THE INSTRUMENT AIR SERVICE WILL NOT BE COMPLETELY INTERRUPTED.

A REVIEW HAS BEEN MADE OF ALL EVENTS ANALYZED IN THE GINNA STATION UFSAR AND EVENTS REQUIRING ANALYSXS BY USNRC REG. GUIDE 1.70 AND GINNA PROCEDURE A-303. THE DESIGN BASIS EVENTS THAT ARE APPLICABLE TO THIS MODIFICATION ARE:

LOSS OF ALL AC POWER TO THE STATION AUXILIARIES LOSS OF NORMAL FEEDWATER FLOW INCREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM WHILE THE INSTRUMENT AIR SYSTEM IS CLASSIFIED AS NON-SAFETY RELATED, IT CONTROLS SAFETY AND NON-SAFETY RELATED AOVs. THE VALVES CONTROLLED FAIL TO A SAFE POSITION, PROVIDING ASSURANCE AGAINST LOSS OF FEEDWATER FLOW AND/OR INCREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM.

THIS MODIFICATION WILL NOT IMPACT THE FUNCTION OF THE INSTRUMENT AIR SYSTEM. BY INSTALLING THE NEW VALVE AND FITTINGS CONSISTENT WITH THE SYSTEM DESIGN SPECIFICATIONS, THERE WILL BE NO IMPACT ON SYSTEM FUNCTXONS DURING NORMAL OR ACCIDENT CONDXTIONS. THEREFORE, PLANT RESPONSE TO ANY DESIGN BASIS ACCIDENT WILL REMAIN UNCHANGED THUS, THE MODIFICATION NEITHER INCREASES THE CONSEQUENCES, NOR DOES IT REDUCE THE MARGIN OF SAFETY FOR INTERNAL EVENTS INVOLVING:

LOSS OF ALL AC POWER TO THE STATION AUXILIARIES LOSS OF NORMAL FEEDWATER FLOW INCREASE XN HEAT REMOVAL BY THE SECONDARY SYSTEM

BASED UPON A REVIEW OF THE UFSAR AND THE REQUIREMENTS OF PROCEDURE A 303 AND GINNA STATION TECHNICAL SPECIFICATIONS'T HAS BEEN CONCLUDED THAT WITH NO EFFECT ON EITHER INSTRUMENT AIR OR ANY SAFETY SYSTEM, THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED. "

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURESi SYSTEMS'ND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

SECTION B COMPLETED STATION MODIFICATIONS (SMs)

This section contains a description of station modification procedures performed in the facility as described in the safety analysis report. Station modification procedures are written to complete a portion of an Engineering Work Request (EWR) or Technical Staff Request (TSR) identified by the same parent number. Station Modifications are reviewed by the Plant Operations Review Committee to ensure that no unreviewed safety questions or Technical Specification changes are involved with the procedure.

The basis for inclusion of an SM in this section is closure of the SM where portions of the parent EWR or TSR, in the form of other SMs or other documentation, remain to be completed.

SM-89-06.1 DZ AN SA 3 4" UX LIARY BUILDING PIPE SUPPORTS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE NEW PERMANENT PIPE SUPPORTS ADDED TO THE 3/4" DI SUPPLY LINE AND 3/4" SERVICE AIR SUPPLY LINE TO THE AUXILIARY BUILDING OPERATING FLOOR.

SM-89-07.1 OUTSIDE COND NSATE STORAGE TANK TRANSFER LINE INSTALLATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING AND TURNOVER OF A 2 1/2 INCH DIAMETER LINE WITH APPROPRIATE VALVING FROM THE DISCHARGE OF THE A AND B REGENERATION SLUICE PUMPS TO THE DISCHARGE OF THE CONDENSATE TRANSFER PUMP UPSTREAM OF CHECK VALVE 9505G.

SM-89-20.1 UXI ZARY BUILDING EXHAUST FAN B CONDUIT SUPPORT THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THIS MODIFICATION WHICH INVOLVES AN UPGRADE TO AN EXISTING CONDUIT SUPPORT FOR THE AUXILIARY BUILDING EXHAUST FAN B AND ALLOW REMOVAL OF THE SUPPORT WHEN MAINTENANCE IS REQUIRED ON THE FAN.

SM-89-30.1 S C ECK VALVE 1828 TEST CONNECTION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF SI CHECK VALVE 1828 TEST CONNECTION SM-2504.27 CON N MI I- GE EXHAUS S STEM ELEC ICAL ACCEPTANCE EST THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE ELECTRICAL ACCEPTANCE TESTING, AND TURNOVER OF THE CONTAINMENT MINI-PURGE EXHAUST SYSTEM AT PENETRATION 132 AND THE STATUS LIGHTS FOR V5869~ V5879~ AND V5392 ~

SM-2504.28 CONTAINMENT MINI-PURGE SYSTEM PERFORMANCE EST THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING AND TURNOVER OF THE CONTAINMENT MINI-PURGE SYSTEM.

SM-2512.139 SEISMIC UPGRADE OF PIPE SUPPORTS ANALYSIS LINE SW-2100 SERVICE WATER SUCTION AND SUCTION CROSS-TIE TO nDn SAFW PUMP THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF PIPE SUPPORT MODIFICATIONS TO THE SERVICE WATER LINE FORMING SUCTION AND SUCTION CROSS-TIE FEED TO THE "D" SAFW PUMP NOT PREVIOUSLY COMPLETED UNDER SM-2512.127. A 10CFR50.59 REVIEW

WAS CONDUCTED AND BASED ON A REVIEW OF TECH. SPECS DESIGN CRITERIA AND SAFETY ANALYSIS IT HAS BEEN CONCLUDED THAT THE MARGINS OF SAFETY DURING NORMAL OPERATIONS AND TRANSIENT CONDITIONS ANTICIPATED DURING THE LIFE OF THE PLANT HAVE NOT BEEN REDUCED.

IT HAS ALSO BEEN CONCLUDED THAT THE ADEQUACY OF STRUCTURES, SYSTEMS AND COMPONENTS PROVIDED FOR THE PREVENTION OF ACCIDENTS AND THE MITIGATION OF THE CONSEQUENCES OF ACCIDENTS HAVE NOT BEEN AFFECTED BY THE IMPLEMENTATION OF THIS MODIFICATION.

SM-2512.141 SEISMIC UPGRADE OF PIPE SUPPORTS REWORK OF FEEDWATER SUPPORTS FWU-37 AND FWU-41 ON ANALYSIS LINE FW-300 THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE ISTALLATION AND TURNOVER OF MODIFICATIONS TO PIPE SUPPORTS FWU-37 AND FWU-41 ON MAIN FEEDWATER PIPING..

EWORK OF SERVICE WATER SUPPORT SWU-153 ON 20" SERVICE WATER LINE IN THE AUXILIARY BUILDING - ANALYSIS LINE SW-1100 THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF SUPPORT SWU-153 FOR THE 20" SERVICE WATER LINE IN THE AUXILIARY BUILDING AT ELEVATION 265 -3" SM-3258.4 WO 0 SE SM C GE OX SUPPO FO SE V CE WATER VALVE 4644 THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF VALVE 44644 SEISMIC SUPPORT IN ACCORDANCE WITH NCR 91-060.

SM-3595.12 FUNCT ON L TEST OF CONT OL OO VEN ILATION S STEM THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING AND TURNOVER OF THE MODIFICATIONS MADE TO THE CONTROL ROOM VENTILATION SYSTEM AND VENTILATION MONITORS'M-3596.11 D ESEL GENERATOR AND TUB G PROTECTION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF TUBING PROTECTION ON THE FLOOR BETWEEN THE INSTRUMENT PANELS AND DIESEL GENERATOR SKIDS FOR THE A AND B DIESEL GENERATORS.

SM-3596.13 DIESEL G NERATOR "B" AIR START SYSTEM MECHANICAL UPGRADE THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE MECHANICAL UPGRADE AND TURNOVER OF THE AIR START SYSTEM FOR THE t'B't DIESEL GENERATOR

D G n n AIR STAR UPGRADE ES ING THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING AND TURNOVER OF D/G nAn AIR START SYSTEM UPGRADE-SM-3596.15 D G n n AIR START UPGRADE ES ING THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING AND TURNOVER OF THE D/G nBn AIR START SYSTEM UPGRADE.

SM-3596.16 D ES G NERA OR A AND B NSTRUMENT TUBING GUARDRAILS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF GUARDRAILS AROUND THE DAY TANK LEVEL TRANSMITTERS AND INSTRUMENT TUBING FOR THE A AND B DIESEL GENERATORS.

SM-3681.2 INSTALLATION OF PULL POINTS FOR THE GSU TRANSFORMER REPLACEMENT THE LIAISON ENGINEER PRESENTED THIS PROCEDURE FOR FINAL CLOSEOUT AND DELETION. THIS WORK WAS COMPLETED IN 1986 AND THE PROCEDURE SUBSEQUENTLY LOST. A WALKDOWN OF THE CONSTRUCTION WAS RECENTLY PERFORMED BY A LIAISON ENGINEER AND AN ESD ENGINEER TO VERIFY PROPER INSTALLATION.

SM-3797.12 MRPI SYSTEM GROUND FAULT MON TORING I STALLATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF MODIFICATIONS TO THE MRPI SYSTEM TO PROVIDE MONITORING FOR SYSTEM FAULTS.

SM-3881.4 SI SYSTEM HYDROSTATIC AND SYSTEM FUNC ONAL TEST THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING AND TURNOVER OF THE SI RECIRC SYSTEM.

SI RECIRCULATION SYSTEM RE-TEST THE LIAISON ENGINEER PRESENTED THIS PCN TO THE COMMITTEE.

IT REQUESTED CHANGES BE MADE TO RE-PERFORM SI FULL FLOW VERIFICATION TEST.

SM-3881.6 BORIC AC D STORAGE TANKS OVERFLOW P PING MOD FICATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE BORIC ACID STORAGE TANK(S) OVERFLOW PIPING MODIFICATION.

SM-3881.9 SAFET NZECTION PUMP RECI CU TION PRESSURE GAUGE RELOCATION AND VALVE 874B REPLACEMENT THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF SAFETY INJECTION RECIRCULATION PRESSURE GAUGES (PZ REPLACEMENT.

912'13'14'ND 915) RELOCATION AND VALVE 874B DIESE GENERATOR BUILDING IMPINGEMENT ODIFICATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE I I I I RELO CAT ON/ NSTALLAT ON ~ TEST NG g AND TURNOVER OF THE BELOW GRADE ROOF DRAINS, BELOW GRADE FIRE SERVICE WATER LINE, BELOW GRADE OUTDOOR GROUNDING, AND ALTERNATE COOING WATER SUPPLY STUB-UPS ADTACENT TO THE DIESEL GENERATOR BUILDING. ALSO INCLUDED ARE THE CIVIL WORKS THROUGH AND INCLUDING EXCAVATION, FOOTERS, STEM WALLS, GRADE BEAMS, BACKFILL (AS REQUIRED) AND MISCELLANEOUS APPURTENANCES. THZS PROCEDURE GENERICALLY COMPLETES THE BELOW GRADE AND FOUNDATION ERECTION ITEMS PREVIOUSLY COMMENCED UNDER SM-3990.3.

SM-3990.6 DIESEL GENERATOR BUILDING ARAPET WALL MODIFICATIONS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE DIESEL GENERATOR BUILDING PARAPETS AND WALLS.

SM-3990.8 DIESEL GENERATOR BUILDING ROOF SLAB MISSILE DOOR AND INTAKE CANOPY MODIFICATIONS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, AND TURNOVER OF THE D/G BUILDING ROOF SLAB, INCLUDING MUFFLER PIPING REWORK, HVAC COMPONENTS, ROOF DRAINS AND STRUCTURAL STEEL COMPONENTS.

SM-3990.9 D ESEL GENERA OR BUILD NG S NKLER ADDITION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF SPRINKLER SYSTEMS ADDITIONS IN THE DIESEL GENERATOR BUILDING.

SM-3990.10 F SERVICE Y D LOOP MODIFICATION WEST SIDE THE PURPOSE OF THIS PROCEDURE ZS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE FIRE SERVICE YARD LOOP FOR NEW TRAILERS M-3

A B D ES GENERATOR ROOM ALCOVE L GHTZNG THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF ADDITIONAL LIGHTING FIXTURES LOCATED IN THE PERSONNEL DOOR ALCOVES.

SM-4068.8 RMS AREA MONITOR PRE-AMP CHANGEOUT THE PURPOSE OF THIS PROCEDURE IS TO PROVIDE INSTRUCTION FOR THE REPLACEMENT OF THE DETECTOR PREAMP MODULE IN THE RMS AREA MONITORS'M-4068.9 R-15 AIR EJECTOR RADIA ION MON TO DETECTOR ELECTRICAL MO F C IONS AN REMOVALS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE ELECTRICAL PORTION OF THE NEW R-15, AIR EJECTOR RADIATION MONITOR DETECTOR MODIFICATION.

SM-4068.11 R-16 CON AINMENT FAN COOLING RADIATION MONITOR DETECTOR-ELECTRICAL MODIFICATIONS D REMOVALS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE ELECTRICAL PORTION OF THE NEW R-16, CONTAINMENT FAN COOLING RADIATION MONITOR DETECTOR MODIFICATION

-17 COMPONENT COOLING WATER DIATION MONITOR DETECTOR-LEC A 0 CA IO S EMOVA THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE ELECTRICAL PORTION OF THE NEW R-17, COMPONENT COOLING WATER RADIATION MONITOR DETECTOR MODIFICATION.

SM-4068.14

-18 WASTE LI UID RADIAT ON MONITOR DETECTOR MECHANICAL OD F CATIONS AN REMOVALS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE MECHANICAL PORTION OF THE NEW R-18, WASTE LIQUID RADIATION MONITOR DETECTOR MODIFICATION. ALSO, THE WESTINGHOUSE EXPERIMENTAL Ge(Li) LIQUID WASTE DETECTOR (LOCATED JUST SOUTH OF THE EXISTING R-18) WILL BE REMOVED.

SM-4068.15 R-18 WASTE LI UID RADIATION MONITOR DETECTOR ELECTRICAL MODIFICATIONS AND REMOVALS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE ELECTRICAL PORTION OF THE NEW R-18, WASTE LIQUID RADIATION MONITOR DETECTOR MODIFICATION.

SM-4068.17 R-19 STEAM GENERATOR BLOWDOWN RADIATION MONITOR DETECTOR-ELECTRICAL MODIFICATIONS AND REMOVALS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE ELECTRICAL PORTION OF THE NEW R-19, STEAM GENERATOR BLOWDOWN RADIATION MONITOR DETECTOR MODIFICATION.

SM-4068.18 R-20A SPENT FUEL POOL HEAT EXCHANGER nAn SERVICE WATER RADIATION MONITOR DETECTOR MECHANICAL MODIFICAT ONS AND REMOVALS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE MECHANICAL PORTION OF THE NEW R-20A, SPENT FUEL POOL HEAT EXCHANGER nAn SERVICE WATER RADIATION MONITOR DETECTOR MODIFICATION.

SM-4068.19 R-20A SPENT FUEL POOL HEAT EXCHANGER nAn SERVICE WATER RADIATION ONITOR DETECTOR - ELECTR CAL MODIFICA ONS AND REMOVALS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE ELECTRICAL PORTION OF THE NEW R-20A, SPENT FUEL POOL HEAT EXCHANGER nAn SERVICE WATER RADIATION MONITOR DETECTOR MODIFICATION.

SM-4068.20 DI ON 0 0 SYSTEM CAB N S S- N RMS-3 MOD FICATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE ELECTRICAL MODIFICATIONS TO RMS-1 AND RMS-3 CABINETS.

5 CT ON L TES THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE FUNCTIONAL TESTING AND TURNOVER OF R-15, AIR EJECTOR RADIATION MONITOR.

SM-4068.22 R-16 FUNCTIONAL TEST THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE FUNCTIONAL TESTING AND TURNOVER OF R-16, CONTAINMENT FAN COOLING RADIATION MONITOR.

SM-4068.23

-17 FUNCTION L TEST THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE FUNCTIONAL TESTING AND TURNOVER OF R-17, COMPONENT COOLING WATER RADIATION MONITOR.

S -4068.24

8 CT ONA EST THE PURPOSE OF THIS PROCEDURE IS FOR R-18 FUNCTIONAL TEST.

SM-4068.25

-1 FUNCTION L TEST THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE FUNCTIONAL TESTING AND TURNOVER OF R-19, STEAM GENERATOR BLOWDOWN RADIATION MONITOR.

SM-4068.26 R-20A FUNCTIONAL TEST THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE FUNCTIONAL TESTING AND TURNOVER OF R-20A, SFP HEAT EXCHANGER A RADIATION MONITOR.

SM-4068.27 R-20B FUNCTIONAL TEST THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE FUNCTIONAL TESTING AND TURNOVER OF R-20B, SFP HEAT EXCHANGER B PROCESS MONITOR.

SM-4112.1 UXIL ARY BUILD NG OPERAT NG FLOOR GH ING UPGRADE THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTZNGt AND TURNOVER OF NEW LIGHTING FIXTURES ON THE AUXILIARY BUILDING OPERATING LEVEL.

SM-4218.5 SEISMIC UPGRADE S EAM GENERATOR LEVEL NSTRUMENTATION TUBING SUPPORTS ASSOC A ED WITH T-460 AND LT-460A THE PURPOSE OF THIS PROCEDURE ZS TO CONTROL THE INSTALLATION AND TURNOVER OF STEAM GENERATOR LEVEL INSTRUMENTATION TUBING SUPPORTS ASSOCIATED WITH LT-460 AND LT-460A.

SM-4218.13 SEISMIC UPGRADE - STEAM GENERATOR "B" LEVEL NSTRUMENTATION TUBING AND SUPPORTS ASSOCIATED WITH L -472 THE PURPOSE OF THIS PROCEDURE IS TO DOCUMENT/DIRECT REWORK OF LT-472 TUBING AND SUPPORTS.

SM-4218.18 SEISMIC UPGRADE STEAM GENERATOR B LEVEL INSTRUMENTATION TUBING AND SU PORTS ASSOC ATED WITH LT-470 IN TH "B" LOOP AREA THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF STEAM GENERATOR LEVEL INSTRUMENTATION TUBING AND REQUIRED SUPPORTS ASSOCIATED WITH WIDE RANGE

I TRANSM TTERS LT 4 7 0 i IN THE B LOOP AREA PERMANEN CONDUIT CABLE AND FOXBORO RACK INSTALLATION AND TESTING-G S EAM DOME P ESSUR SM TE PIT-510 511 THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF PERMANENT ELECTRICAL CONNECTIONS BETWEEN TRANSMITTERS PIT-510/511 AND PPCS MUX CABINET 1, TO INCLUDE ALL CABLE, CONDUIT AND SUPPORTS'ONNECTIONS AND MODULE INSTALLATION IN FOXBORO RACK g3.

SM-4223.1 RETENTION TANK H CONTROL DRAIN TRENCH MODIFICATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE RETENTION TANK pH CONTROL DRAIN TRENCH MODIFICATION.

SM-4225.4 INSTALLATION AND TESTING OF AMPTECTOR OVERCURRENT DEVICES THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF AMPTECTOR OVERCURRENT DEVICES FOR THE DB 25i DB 50i AND DB 75 WESTINGHOUSE BREAKERS'M-4225.5 INSTALLATION AND TESTING OF LOCAL PUSHBUTTONS FOR 480V BREAKERS ON BUS 13 AND BUS 15 THE PURPOSE OF THIS PROCEDURE IS TO DIRECT INSTALLATION AND TESTING OF LOCAL PUSHBUTTONS.

SM-4225.6 INSTALLATION VERIFICATION AND TES ING OF LOCAL PUSHBUTTONS FOR 480V BREAKERS ON BUS 13 AND BUS 5 THE PURPOSE OF THIS PROCEDURE IS TO VERIFY THE INSTALLATION AND TO PERFORM TESTING OF LOCAL PUSHBUTTONS FOR LISTED BREAKERS ON BUSES 13 AND 15.

SM-4225.20 NSTALLATION AN TESTING OF AN AMPTECTO OVERCURRENT DEVICE FROM KIT 8184A50G08 ON BUS 13 7 GENE OR RANSFORMER AUXILIARY POWER SUPPLY 1A THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF AN AMPTECTOR OVERCURRENT DEVICE FOR THE DB-25 WESTINGHOUSE BREAKER ON BUS 13, POSITION 7D (GENERATOR TRANSFORMER AUX. POWER SUPPLY 1A) EMPLOYING AN AMPTECTOR FROM KIT 48184A50G08.

INSTAL ON D TESTING OF AN AM ECTOR OVERCURRENT DEVICE FROM

8 OG08 BUS 3 G 0 RANS FORMER UX I POWE SU P Y B THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATIONS TESTING, AND TURNOVER OF AN AMPTECTOR OVERCURRENT DEVICE FOR THE DB-25 WESTINGHOUSE BREAKER ON BUS 15, POSITION 3D (GENERATOR TRANSFORMER AUX. POWER SUPPLY 1B) EMPLOYING AN AMPTECTOR FROM KIT 08184A50G08.

SM-4225.22 INSTALLATION AND TESTING 0 AN AMPTECTO OVERCURRENT DEVICE FOR A SP nCn SI PUMP BREAKER THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING AND TURNOVER OF AN AMPTECTOR KIT, APPLIED TO A SPARE BREAKER SUITED FOR THE SUPPLY OF THE "C" SI PUMP FROM EITHER BUS 14 OR BUS 16

'M-4324.16 S G BLOWDOWN VALVE INDICATIONS REWORK NCR G89-740 THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE REWORK, TESTING AND TURNOVER OF THE A AND B S/G BLOWDOWN MANUAL FLOW CONTROL VALVES FCV-5725A AND FCV-5725B VALVE POSITION INDICATION LIGHTS ON THE S/G BLOWDOWN PANEL SM-4526.20 D G FUEL OIL SYSTEM PUMPING STATION INSTRUMENTATION ELECTRICAL PORTION THE PURPOSE OF THIS PROCEDURE IS TO INSTALL THE ELECTRICAL PORTION OF THE D/G FUEL OIL SYSTEM PUMP STATION INSTRUMENTATION.

THE COMMITTEE REVIEWED AND RECOMMENDED APPROVAL OF THIS NEW PROCEDURE. THE FOLLOWING DOCUMENTATION IS PROVIDED AS JUSTIFICATION FOR COMPLIANCE WITH 10 CFR 50 59.

REFERENCES:

UFSAR, TECH. SPECS. JUSTIFICATION: THIS MODIFICATION IS ADDED TO GIVE AN INDICATION OF TRANSFER PUMP DISCHARGE PRESSURE AND SUCTION STRAINER DP THOSE PORTIONS AFFECTING SAFETY SYSTEMS ARE QUALIFIED, OTHER PORTIONS DO NOT AFFECT PLANT SAFETY SM-4526.23 DIESE GENERATOR DAY ANK I STRUMENTAT ON PHASE 2 AND FUEL RANSFE PUMP A AND B AUTO FUNCTION REMOVAL THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION OF THE ELECTRICAL PORTION OF THE DAY TANK INSTRUMENTATION UPGRADE PHASE 2 ON THE 1A DIESEL GENERATOR. IN ADDITION, THIS PROCEDURE WILL PROVIDE INSTRUCTION FOR FILL AND BYPASS SOLENOID VALVE DETERM/RETERM AND MODIFICATION OF FUEL TRANSFER PUMP START CIRCUIT.

SM-4526.24 1B DIESEL GENERATOR DAY TANK INSTRUMENTATION PHASE 2 AND FUEL TRANSFER PUMP A AND B AUTO FUNCTION REMOVAL

THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION OF THE ELECTRICAL PORTION OF THE DAY TANK INSTRUMENTATION UPGRADE PHASE 2 ON THE 1B DIESEL GENERATOR IN ADDITXON, THIS PROCEDURE WILL PROVIDE INSTRUCTION FOR FILL AND BYPASS SOLENOID VALVE DETERM/RETERM AND MODIFICATION OF FUEL TRANSFER PUMP START CIRCUIT.

D G " n FUEL OIL SYSTEM UPGRADE PHASE 3 ELECTRICAL MODIFICATIONS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION OF THE ELECTRICAL PORTION OF THE nAn DIESEL GENERATOR INSTRUMENTATION UPGRADE, INCLUDING THE FOLLOWING: DAY TANK FILL/RECIRC SOLENOID VALVE WX RING, FUEL OZ L TRANSFER PUMP DISCHARGE PRESSURE TRANSMITTER, FUEL OIL TRANSFER STRAINER D/P TRANSMITTER, DAY TANK LEVEL TRANSMITTER.

SM-4526.29 D G nBn FUEL OIL SYSTEM UPGRADE PHASE 3 ELECTRICAL MODIFICATIONS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE COMPLETION OF THE INSTALLATION OF THE ELECTRICAL PORTION OF THE nBn DIESEL GENERATOR INSTRUMENTATION UPGRADE, INCLUDING THE FOLLOWING: DAY TANK FILL/RECIRC SOLENOID VALVE WIRING, FUEL OIL TRANSFER PUMP DISCHARGE PRESSURE TRANSMITTER, FUEL OIL TRANSFER STRAINER D/P TRANSMITTERi DAY TANK LEVEL TRANSMITTER.

SM-4526.30 nAn D G FUEL OXL SYSTEM UPGRADE TESTING THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING AND TURNOVER OF THE nAn DIESEL GENERATOR FUEL OIL SYSTEM ELECTRICAL AND MECHANICAL UPGRADE.

SM-4526.31 nBn D G FUEL OIL SYSTEM UPGRADE TESTING THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING, AND TURNOVER OF THE nBn DIESEL GENERATOR FUEL OIL SYSTEM ELECTRXCAL AND MECHANICAL UPGRADE.

SM-4618.3 MAIN FEED PUMP ROOM DAMPER WIND SCREENS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE MAXN FEED PUMP ROOM DAMPER WIND SCREENS AND WALL HYDRANT EXTENSIONS.

SM-4618.4 MA N EED PUMP ROOM WINDOW REPLACEMENT THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE MAIN FEED PUMP ROOM WINDOW REPLACEMENT.

SM-4658.1 nAn COMPONENT COO ING W TE H AT C GER TEST INSTRUMENTATION INST L T ON THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE nAn COMPONENT COOLING WATER HEAT EXCHANGER TEST INSTRUMENTATION INSTALLATION nAn RCS HOT LEG RHR FLOW CORRECTION

,"U ILIZING NEW INSTRUMENTATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING ASSOCIATED WITH FIELD DATA VERIFICATION OF THE nAn RCS HOT LEG LOOP LEVEL CORRECTION AS A RESULT OF RHR FLOW. THIS TEST IS BEING PERFORMED IN CONJUNCTION WITH PROCEDURE 0-2.3 1 SM-4675.10 3 4n RHR VALVE PRESSURE RELIEF PIPING SEISMIC UPGRADE THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THREE NEW SEISMIC SUPPORTS ON THE RHR-300 BYPASS LINES.

SM-4755.3 "A" SFP PUMP DISCHARGE LINE ANNUBAR F W INDICATOR INSTALLATION AN TESTING THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE ANNUBAR IN THE nAn SFP PUMP DISCHARGE LINE.

SM-4755.4 IST HYDRO TES CONNECTIONS VALVE 2205 AND 2209 CVCS CHARGING THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF HYDRO TEST CONNECTIONS FOR CVCS CHARGING LINE VENT VALVE 2209 AND DRAIN VALVE 2205.

SM-4760.1 MOV 856 CONTRO OWE THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE MODIFICATION TO INSTALL A KEY SWITCH FOR CONTROL POWER TO MOV 856.

SM-4760.2 OV CO 0 OW C 0 S THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING OF CONTROL POWER KEY SWITCH FOR MOV 856.

SM-4773.5 RELOCA 0 OF REACTOR COOLAN DRA N TANK PUMP A CONTROL SWITCH

THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE REACTOR COOLANT DRAIN TANK PUMP A CONTROL SWITCH. THE SWITCH IS TO BE RELOCATED FROM THE MCB CENTER SECTION TO THE LEFT SECTION.

SM-4773.6 0 0 ACTOR COOLANT RAI AN PUMP B CONTROL SWITCH THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE REACTOR COOLANT DRAIN TANK PUMP B CONTROL SWITCH. THE SWITCH IS TO BE RELOCATED FROM THE MCB CENTER SECTION TO THE LEFT SECTION..

SM-4773.7 LOCA ION OF CONTAINMENT AND PLANT EV CUATION ALARM SWITCHES THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF. THE CONTAINMENT AND PLANT EVACUATION ALARM SWITCHES. THE SWITCHES ARE TO BE RELOCATED FROM THE MCB FRONT LEFT SECTION TO THE LEFT SIDE OF THE MCB.

SM-4773.8 REACTO P OTE ON RACK MOD F CATIONS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE MODIFICATION TO THE REACTOR PROTECTION RACK R2i PLP RACKi AND SD RACK PROJECTS PERSONNEL WILL REMOVE/INSTALL/SPLICE CABLE WHILE I&C PERSONNEL WILL REMOVE OLD FOXBORO MODULES AND INSTALL NEW ISOLATION AMPLIFIERS WITH ASSOCIATED WIRING.

SM-4773.9 REAC OR P OTECTION RACK W2 MODIFICATIONS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE MODIFICATION TO THE REACTOR PROTECTION RACK W2, PLP RACK, AND SD RACK. PROZECTS PERSONNEL WILL REMOVE/INSTALL/SPLICE CABLE WHILE I&C PERSONNEL WILL REMOVE OLD FOXBORO MODULES AND INSTALL NEW ISOLATION AMPLIFIERS WITH ASSOCIATED WIRING.

SM-4773.11 C 0 P 0 E ON RACK 2 OD F C IONS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE MODIFICATION TO THE REACTOR PROTECTION RACK Y2, PLP RACK, AND SD RACK. PROJECTS PERSONNEL WILL REMOVE/INSTALL/SPLICE CABLE WHILE I&C PERSONNEL WILL REMOVE OLD FOXBORO MODULES AND INSTALL NEW ISOLATION AMPLIFIERS WITH ASSOCIATED WIRING S G NS RUMENTATION INSIDE CONTA NT

THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF CONDUIT AND CABLES FOR THE 'S/G A INSTRUMENTATION PORTION OF THE ADFCS MODIFICATION. THIS NEW INSTRUMENTATION IS FT-498, LT-460, LT-504 AND LT-505.

S G NS RUMENT TION INS E CON A THE PURPOSE OF THIS NEW PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF CONDUIT AND CABLES FOR THE S/G A INSTRUMENTATION PORTION OF THE ADFCS MODIFICATION. THIS NEW INSTRUMENTATION IS FT-499, LT-470, LT-506 AND LT-507.

CAB MOVALS FOR ADFCS MO I ICA ON THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE DISCONNECTION AND TURNOVER OF CABLE AND COMPUTER TAPS NO LONGER REQUIRED DUE TO THE ADFCS MODIFICATION.

SM-4773.15 RVLMS RACK 1 CABLE INSTALLATION FOR S G WIDE RANGE LEVEL INSTRUMEN TION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF CONDUIT AND CABLES FOR THE WIDE RANGE S/G LEVEL INSTRUMENTATION PORTION OF THE ADFCS MODIFICATION. THIS NEW INSTRUMENTATION WILL BE LOCATED IN THE RVLMS RACK 1.

SM-4773.16 RVLMS RACK 2 CABLE INSTALLATION FOR S G WIDE RANGE LEVEL INSTRUMENTATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF CONDUIT AND CABLES FOR THE WIDE RANGE S/G LEVEL INSTRUMENTATION PORTION OF THE ADFCS MODIFICATION. THIS NEW INSTRUMENTATION WILL BE LOCATED IN THE RVLMS RACK 2 ~

REMOVAL OF FEEDWATE ISOLATION RESE PUSHBUTTONS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE REMOVAL, TESTINGi AND TURNOVER OF THE FEEDWATER ISOLATION RESET PUSHBUTTONS AND ASSOCIATED WIRING THE ABANDONED HOLES SHALL BE UTILIZED BY EWR-5025.

SM-4773.18 E CA ION OF MS V 1A AND MSIV 1B CONTROL SW TCHES THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE MSIV 1A AND MSIV 1B CONTROL SWITCHES.

THE SWITCHES ARE TO BE RELOCATED FROM THE MCB LEFT SECTION TO THE CENTER SECTION.

C CAO BISTABLE STATUS G T MODIFICATION THE PURPOSE OF THIS PROCEDURE ZS TO CONTROL THE INSTALLATION AND TURNOVER OF THE MCB ANNUNCIATOR AND BISTABLE STATUS LIGHT MODIFICATIONS FOR ADFCS. THE S/G LOW LEVEL COINCIDENT WITH STEAM FLOW/FEED FLOW MISMATCH TRIP WILL BE REMOVED FROM THE RX TRIP LOGIC ALONG WITH ASSOCIATED ALIBIS.

SM-4773.21 IN ERMEDIATE BU D NG ELECTR C L WO FOR FEEDWATER AND STEAM FLOW INS NTA ION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF CONDUIT FOR THE NEW FEEDWATER AND STEAM FLOW INSTRUMENTATION PORTION OF THE ADFCS MODIFICATION.

SM-4773.22 TURBINE BUILD NG ELECTRZCA OR FOR FEEDWATER PRESSURE INSTRUMENTATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF CONDUIT AND CABLES FOR THE NEW FEEDWATER PRESSURE INSTRUMENTATION PORTION OF THE ADFCS MODIFICATION.

SM-4773.24 FW V L POS ON CAT ON MODI CATION THE PURPOSE OF THIS PROCEDURE ZS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE MFW I/P TRANSDUCER AND VALVE POSITION INDICATION CABLE MODIFICATION.

SM-4773.26 MFW AND MFW BYPASS EGULATING VALVE BAILEY POSITIONER REPLACEMENT THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF BAILEY VALVE POSITIONERS FOR THE MFW REGULATING VALVES (FCV-466) AND FCV-476) AND THE MFW BYPASS REGULATING VALVES (FCV-480 AND FCV-481) ~

SM-4773.27 SAC CK WORK AN S NG THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TESTING OF NEW MODULES INTERNAL TO THE FOX 3 RACK FOR THE AMSAC SYSTEM. THIS WILL BE DONE AS A RESULT OF THE INSTALLATION OF THE ADVANCED DIGITAL FEEDWATER CONTROL SYSTEM.

SM-4773.28 EAC OR LOGIC CK AND RSC RACK MO IF CATIONS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF THE REACTOR LOGIC RACK AND ROD SPEED CONTROL (RSC) RACK MODIFICATIONS. THE S/G LOW LEVEL COINCIDENT

WITH STEAM FLOW/FEED FLOW MISMATCH TRIP WILL BE REMOVED AS A RESULT OF THE INSTALLATION OF THE ADVANCE DIGITAL FEEDWATER CONTROL SYSTEM.

SM-4833.1 SAS PPCS NERP COMMUNICATION CABLE ZNSTALLAT ON THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF MANHOLESg CONDUIT'ND FIBER OPTIC CABLES BETWEEN THE FOLLOWING AREAS: THE SIMULATOR BUILDING, BROOKWOOD TRAINING CENTER, THE TECHNICIAN SUPPORT CENTER, AND THE GUARDHOUSE.

B RHR LOOP ENHANCEMENTS - MECHANICAL THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION OF THE INSTRUMENTATION AND ASSOCIATED EQUIPMENT IN CONNECTION WITH THE nBn RHR SYSTEM REPLACEMENT OF HEAT TRACE CIRCUIT 29 BORIC ACID BLENDER AREA THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING AND TURNOVER OF THE NEW CHEMELEX SELF REGULATING HEAT TRACE CABLE FOR CIRCUIT $ 29 (BORIC ACID BLENDER AREA PIPING).

SM-4937.7 REPLACE N OF A RACE RCUIT E-6 0 ZC CID FILTER THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATZONi TESTING AND TURNOVER OF THE NEW CHEMELEX SELF-REGULATING HEAT TRACE FOR CIRCUIT gE-6 (BORIC ACID FILTER) ~

SM-4960.1 AGAS T ELAY RELAY EP CEME S OR THE 990 OUTAGE I

THE PURPOSE OF TH S PROCEDURE I S TO CONTROL THE INSTALLATIONi TESTING AND TURNOVER OF AGASTAT TIME DELAY RELAY REPLACEMENTS SCHEDULED TO BE REPLACED DURING THE 1990 OUTAGE.

SM-4960.3 AGASTAT TIME DELAY RELAY REPLACEMENT TDR-1A3 AND TDR-1B3 THE PURPOSE OF THIS PROCEDURE ZS TO CONTROL THE INSTALLATION, TESTING, AND TURNOVER OF AGASTAT TIME DELAY RELAY REPLACEMENT FOR TDR-1A3 AND TDR-1B3 DURING THE 1991 OUTAGE. THE SPECIFIC TESTING TO BE DONE WILL ENSURE THAT THE CIRCUITRY FOR THE DC AUXILIARY OIL PUMPS TO THE MAIN FEEDWATER PUMPS WILL BE OPERATIONAL FOR THE CONDITIONS CONTROLLED BY THE AGASTAT TIME DELAY RELAYS TDR-1A3 AND TDR-1B3.

SM-4960.4 AGASTAT TIME DELAY RELA REPLACEMENTS FOR THE FEEDWATER PUMP LOSS OF SEA WATER TRIP

THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION/

TESTING AND TURNOVER OF AGASTAT TIME DELAY RELAY REPLACEMENTS FOR THE FEEDWATER PUMP (FWP) LOSS OF SEAL WATER TRIP. THE TIME DELAY FOR TRIP OF THE FWP FOLLOWING A LOSS OF SEAL WATER WILL ALSO BE CHANGED FROM 5 TO 60 SECONDS TO PREVENT UNNECESSARY TRIPS OF THE FWPs.

INTRUS ON DETECT ON SYSTEM GUARD HOUSE THE PURPOSE OF THIS PROCEDURE IS TO INSTALL A NEW nEn FIELD PERIMETER ON THE GUARD HOUSE.

SM-5097.2 UNIT CON A NMENT RECIRCULATION PLENUM MODIFICATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE UNIT 1A RECIRCULATION PLENUM MODIFICATION.

nAn STEAM GENERATOR INSULATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE nAn STEAM GENERATOR INSULATION nAn STEAM GENERA OR INSULATION SUPPORT STEEL THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION OF THE nAn STEAM GENERATOR INSULATION SUPPORT STEEL.

SM-5168.2 SCREENHOUSE FLOOR AREA CHLO INE NJECTION PIP NG INSTALLATION THE PURPOSE OF THIS PROCEDURE IS INSTALL CHLORINE INJECTION PIPING IN THE SCREENHOUSE FLOOR AREA TO PROVIDE ZEBRA MUSSEL CONTROL.

SM-5168.7 SCREENHOUSE SERVICE WATER SUPPLY CHLORINE MONITOR ELECTRICAL THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE ELECTRICAL PORTION OF THE SERVICE WATER SUPPLY CHLORINE MONITOR IN THE SCREENHOUSE.

SM-5168.9 TURBINE BUILDING SERV C WATER DZSCHARGECHLORINE MONITOR ELECTRICAL INSTALLATION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE ELECTRICAL PORTION OF THE SERVICE WATER DISCHARGE CHLORINE MONITOR IN THE TURBINE BUILDING.

SM-5168.10 INTERMEDIATE BUILDING SERVICE NATE DISCHARGE CHLORINE MONITOR E C C N TZON THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION AND TURNOVER OF THE ELECTRICAL PORTION OF THE SERVICE WATER DISCHARGE CHLORINE MONITOR IN THE INTERMEDIATE BUILDING-S - 6 SC OUS C LO I E MON 0 E CA ESTING THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING AND TURNOVER OF THE ELECTRICAL INSTALLATION OF THE SCREENHOUSE CHLORINE MONITOR.

SM-5168.14 INTERMEDIATE BUILDING SERVICE WATER DISCHARGE CHLORINE MONITOR ELEC CAL TEST G THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE TESTING AND TURNOVER OF THE INSTALLATION OF THE INTERMEDIATE BUILDING SERVICE WATER DISCHARGE CHLORINE MONITOR.

MSZV CONDUIT CABLE RE-ROUTE AND TESTING THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE INSTALLATION, TESTING AND TURNOVER OF CABLE AND CONDUIT RE-ROUTING FOR CONTROL POWER TO BOTH A AND B MSIV SOLENOID VALVES.

GZNNA ELECTRIC DISTRIBUTION SYSTEM STUDY 0 Y E U PMENT S T ON THE PURPOSE OF THIS PROCEDURE IS TO OBTAIN DATA'O VERIFY COMPUTER MODELS OF GINNA STATION WHICH SIMULATE VOLTAGE AND SHORT CIRCUIT CURRENT LEVELS DURING ALL PLANT OPERATING CONDITIONS AND TO CONTROL THE INSTALLATION OF MEASUREMENT EQUIPMENT TO BE TEMPORARILY INSTALLED FOR THIS MODIFICATION.

SM-5295.5 GZNN LECT CAL SYSTEM LOAD S DY - DA A COLLECTION THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE DATA COLLECTION FROM THE RECORDING EQUIPMENT INSTALLED DURING THE OUTAGE.

OTOR D TA COLLEC ON OR SELECTE OTO STAR S THE PURPOSE OF THIS PROCEDURE IS TO OBTAIN DATA TO VERIFY COMPUTER MODELS OF GINNA STATION SAFETY RELATED MOTORS AND TO CONTROL THE INSTALLATIONOF MEASUREMENT EQUIPMENT TO BE TEMPORARILY INSTALLED FOR THIS MODIFICATION THE INSTALLATION OF ALL SUPPORTING TEST INSTRUMENTATION IS NON-INTRUSIVE AND WILL HAVE NO

IMPACT ON THE ASSOCIATED EQUIPMENTS OPERABILITY.

LOAD MEASUREMENTS FOR SELECTED E UIPMENT DURING THE A DIESEL G NE TOR LOA SAFEGUAR SE U E ST THE PURPOSE OF THIS PROCEDURE IS TO OBTAIN DATA TO VERIFY COMPUTER MODELS OF THE GINNA EMERGENCY LOADS AND DIESEL GENERATORS AS WELL AS TO CONTROL THE INSTALLATION AND REMOVAL OF THE TEMPORARILY INSTALLED MEASUREMENT EQUIPMENT.

SM-5295.8 D ME S EMENTS FOR SELECTED E UIPMEN DURING THE B DIESEL GENERATOR LO D AND SAFEGUAR SE UENC TEST THE PURPOSE OF THIS PROCEDURE IS OBTAIN DATA TO VERIFY COMPUTER MODELS OF THE GINNA EMERGENCY LOADS AND DIESEL GENERATORS AS WELL AS TO CONTROL THE INSTALLATION AND REMOVAL OF THE TEMPORARILY INSTALLED MEASUREMENT EQUIPMENT..

GINNA ELECTR CAL SYSTEM LOAD STUDY TEMPORARY MEASURING INSTRUMENTATION REMOVAL THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE REMOVAL OF TEMPORARILY INSTALLED INSTRUMENTATION THAT WAS USED FOR DATA COLLECTION IN RESPONSE TO THE ELECTRICAL DISTRIBUTION SYSTEM FUNCTIONAL SAFETY INSPECTION SM-5393.1 UNITS "A" AND "B" CONT INMENT RECIRCULATION FAN MOTOR COOLER REPLACEMENTS THE PURPOSE OF THIS PROCEDURE IS TO CONTROL THE REMOVAL, INSTALLATION AND TURNOVER OF THE "A" AND "B" CONTAINMENT RECIRCULATION FAN MOTOR COOLERS.

SECTION C COMPLETED TECHNICAL EVALUATIONS (TEs)

This section contains a description of changes to the facility as described in the safety analysis report performed as technical evaluations. These are typically small changes that do not require the full controls of a modification. Technical Staff Engineering Evaluations are reviewed by the Plant Operations Review Committee to ensure that no unreviewed safety questions or Technical Specification changes are involved.

The basis for inclusion of a TE in this'ection is presentation to the PORC, closure of the associated TSR, and submittal to the Document Control Department.

TSR 90-177 TECHNICAL STAFF ENGINEERING EVALUATION DATED ~93 91 REV 0 THE PURPOSE OF THIS EVALUATION IS TO JUSTIFY THE INSTALLATION OF VALVE 9519F, (TURBINE DRIVEN AUXILIARY FEEDWATER PUMP THROTTLE VALVE DRAIN/TRAP INLET DRAIN VALVE) AND ADDITIONAL MINOR PIPING ON A PREVIOUSLY CAPPED NIPPLE DOWNSTREAM OF STEAM DRAIN LINE ISOLATION VALVE 3529 AS INSTALLED UNDER MWRTR 89-3669.

TSR 90-140 SPENT FUEL POOL COOLING SKID MOUNTED PUMP INSTALLATION TECHNICAL STAFF ENGINEERING EVALUATION DATED 8II26 91 REV 1 UNDER EWR 1594B, A SKID MOUNTED PUMP WAS TEMPORARILY INSTALLED IN THE BASEMENT OF THE AUXILIARY BUILDING TO SERVE IN SPENT FUEL POOL COOLING LOOP 3. THIS LOOP SERVES AS A BACKUP TO THE PERMANENT LOOPS 1 AND 2. IT IS REQUIRED TO BE OPERABLE WITHIN SEVERAL HOURS OF A LOOP 2 FAILURE DURING CERTAIN REFUELING SCENARIOS. IN ORDER TO MINIMIZE INSTALLATION TIME AND EFFORT IT IS DESIRED TO LOCATE THE PUMP PERMANENTLY IN ITS CURRENT LOCATION. THE PUMP IS SEISMICALLY MOUNTED TO THE BUILDING STRUCTURE AND IS ISOLATED FROM ANY PROCESS LINES OR THE ELECTRICAL SYSTEM. THEREFORE, THERE IS NO POTENTIAL IMPACT TO SAFETY RELATED EQUIPMENT IN THE AREA DURING NORMAL OR ACCIDENT CONDITIONS.

TSR 91-174 SAFWP C AND D COOLING UNITS TEST POINT INSTALLATION TECHNICAL STAFF ENGINEERING EVALUATION DATED 9II16 91 REV 0 PRESENTLY, A METHOD DOES NOT EXIST TO MEASURE THE AIR FLOW THE SAFWP C AND D COOLING UNITS. THE INSTALLATION OF THE TEST POINTS IS NECESSARY IN ORDER TO VERIFY ACCEPTABLE HEAT EXCHANGER PERFORM-ANCE. THIS EVALUATION WILL PROVIDE EQUIVALENCY BETWEEN THE ORIGINAL CONDITION OF THE SUCTION SIDE DUCTING AND THE PROPOSED ADDITION 1/2" DIAMETER HOLES WITH 1/2" METAL HOLE PLUGS.

TSR 91-189 ELIEF VALVE 5477W SETPOINT INCREASE TECHNZCAL STAFF ENGINEERING EVALUATION DATED 9II24 91 REV 0 THE RELIEF SETPOINT OF VALVE 5477W IS CURRENTLY SET AT 100 PSI.

PER REFERENCE OMM 051'ESTINGHOUSE RECOMMENDS THAT THE SETTING BE INCREASED TO A VALUE OF UP TO 125 PSI MAXIMUM. THIS IS TO BE DONE TO SOLVE PROBLEMS EXPERIENCED SUCH AS HIGH OIL TEMPERATURES AND INADVERTENT OPENING OF THE RELIEF VALVE DURING NORMAL OPERA-TION. NORMAL OPERATING PRESSURE DOWNSTREAM OF THE HYDROGEN SIDE SEAL OIL PUMP IS HIGHER THAN THE CURRENT RELIEF SETTING, AND THUS THE RELIEF VALVE DOES NOT AND CAN NOT SERVE ITS DESIGN FUNCTION.

TSR 91-173 AUX. BLDG. CRANE MAIN HOOK SHEAVE PIN LUBRICATION SYSTEM TECHNICAL STAFF ENGINEERING EVALUATION DATED ~920 91 REV 0 THIS TSEE WILL EVALUATE THE ADDITION OF MANUAL LUBRICATION PORT THROUGH THE CENTER OF THE MAIN HOOK HEADBLOCK SHEAVE PIN TO ENHANCE THE LUBRICATION OF THE SELF-LUBRICATING BUSHING ON THE SHEAVE PIN. THIS LUBRICATION ENHANCEMENT WILL AUGMENT THE SELF-LUBRICATING BUSHINGS BY PROVIDING A POSITIVE FLOW OF GREASE INTO THE AREA UNDER EACH SHEAVE PIN BUSHING AND ELIMINATING THE POTENTIAL FOR THE SHEAVES TO FREEZE TO THE PIN.

THIS FEATURE ADDITION WILL NOT COMPROMISE THE ABILITY OF THE CRANE TO WITHSTAND A DESIGN BASIS EARTHQUAKE. THE POTENTIAL FOR CONTAMINATION OF THE SFP FROM CHEMICAL LEACHING WHEN THE HEADBLOCK IS IMMERSED IN THE POOL HAS BEEN ANALYZED AND FOUND TO BE ACCEP-TABLE. THE LUBRICATION FEATURE WILL IMPROVE CRANE PERFORMANCE AND RELIABILITY. THE MACHINING REQUIRED FOR LUBRICATION PORT INSTALLATION HAS BEEN EVALUATED STRUCTURALLY AND WILL NOT AFFECT CRANE DESIGN LOADINGS.

TSR 91-135 I-2212 RELOCATION TECHNICAL STAFF ENGINEERING EVALUAT1ON DATED ~830 91 REV 0 PI-2212 PROVIDES INDICATION TO THE OPERATOR OF THE PRESSURE DOWNSTREAM OF AOV-3806 (SEAL WATER PRESSURE CONTROL AOV TO VALVE SEALING SYSTEM). WHEN PLACING THE AOV IN SERVICE OR WHEN USING THE BYPASS GLOBE VALVE FOR CONTROL, THE OPERATOR MUST OBSERVE PI-2212. HOWEVER, IT IS LOCATED APPROXIMATELY 25 FEET AWAY AND IS NOT VISIBLE FROM THE LOCATION OF THE AOV.

THE PURPOSE OF THIS EVALUATION IS TO RELOCATE THE PRESSURE GAUGE CLOSER TO THE AOV. THIS WILL INVOLVE THE REPLACEMENT OF SOME OF THE PIPING, REMOVAL OF A LENGTH OF TUBING AND A NEW ATTACHMENT INTO THE RUN PIPE FOR THE GAUGE CONNECTION.

THIS CHANGE AFFECTS ONLY A NON-SAFETY RELATED SYSTEM (CONDENSATE)

AND IS LOCATED SUCH THAT IT HAS NO POTENTIAL IMPACT TO SAFETY RELATED STRUCTURES, SYSTEMS OR COMPONENTS. NO SYSTEM FUNCTION WILL CHANGE AS A RESULT OF THE GAUGE RELOCATION.

TSR 91-117 NRHX DRAIN LINES NIPPLE AND CAP ADDITION TECHNICAL STAFF ENG1NEERING EVALUATION DATED ~10 10 91 REV 0 VALVES 2232 AND 2233, NRHX INLET AND OUTLET (RESPECTIVELY) DRAIN VALVES, HAVE EXPERIENCED SEAT LEAKAGE WHICH HAS IN TURN RESULTED IN THE RELEASE OF BOTH CONTAMINATED WATER AND RADIOACTIVE GASSES TO THE ENVIRONMENT OF THE AUXILIARY BUILDING DURING PERIODS WHEN THE AUXILIARY BUILDING VENTILATION SYSTEM IS OUT OF SERVICE.

THIS EVALUATION WILL PROVIDE JUSTIFICATION FOR THE ADDITION OF TWO 3/4" NPT 3" LONG NZPPLES AND TWO 3/4" NPT THREADED CAPS, ONE TO BE ATTACHED TO THE DOWNSTREAM SIDE OF VALVE 2233 AND THE SECOND TO BE ATTACHED TO THE OPEN TEE DOWNSTREAM OF VALVE 2232.

TSR 91-002 EH RESERVOIR IMMERSION HEATER INSTALLATION TSR 9 1 002 WILL INSTALLF DURING THIS SHUTDOWN g AN IMMERSION HEATER IN THE EH RESERVOIR. THE PURPOSE OF THE HEATER IS TO BRING EH FLUID CLOSER TO OPERATING TEMPERATURE PRIOR TO STARTUP. IT IS INTENDED TO ENERGIZE THE HEATER ONLY DURING PRE-STARTUP OF THE EHC SYSTEM THE HEATER WILL BE MOUNTED ON AN EXISTING FLANGE THAT WAS INSTALLED DURING THE 1991 SHUTDOWN PER THIS TSR AN EXISTING 208 VAC RECEPTACLES CURRENTLY USED ONLY FOR THE EH OIL TRANSFER PUMPF WILL BE UPGRADED FROM A HANGING CORDCAP" TO A PANEL MOUNTED FLANGED RECEPTACLE. THE RECEPTACLE CAN THEN BE UTILIZED TO POWER THE EHC TRANSFER PUMP ~O THE IMMERSION HEATER. IT ZS NOT ANTICIPATED THAT BOTH DEVICES WILL BE REQUIRED SIMULTANEOUSLY. A TSEE AND 50.59 ARE COMPLETE PER A-305.

TSR 92-057 TEMPORARY CONNECTION OF MONITORING E UIPMENT TO EXISTING TEST POINTS THE PURPOSE OF THIS ANALYSIS IS TO EVALUATE THE SAFETY CONSEQUENCES OF CONNECTING TEMPORARY MONITORING INSTRUMENTATION TO EXISTING TEST POINTS. UNDER THE SCOPE OF A-1406'ONNECTING TEMPORARY RECORDERS FOR EXTENDED PERIODS OF TIME IS CONSIDERED A TEMPORARY MODIFICATION. THIS EVALUATION IS BASED ON USING MONITORING INSTRUMENTATION WITH HIGH IMPEDANCE ISOLATED INPUTS CONNECTED TO ESTABLISHED TEST POINTS.

TSR 92-094 VALVE 4051 BLANK FLANGE INSTALLATION TECHNICAL STAFF ENGINEERING EVALUATION DATED 4 II292 REV 0 THIS EVALUATION WILL JUSTIFY THE PERMANENT INSTALLATION OF A CARBON STEEL PLATE AT THE BOLTED FLANGE DOWNSTREAM OF VALVE 4051, MAIN CONDENSER 'tBn CONDENSATE FILL MANUAL VALVE

SECTION D TEMPORARY MODIFICATIONS This section contains descriptions and summaries of safety evaluations of temporary changes pursuant to the requirements of 10 CFR 50.59(b).

8/16/91 SERVICE WATER PUMP C AND D DISCHARGE PT-2028 PRESSURE SENSING LINE REPLACEMENT 91-20 The pressure sensing line for PT-2028 has been isolated at the 1 inch root valve on the Service Water Pump C and D discharge header, due to a leak at a contact point with tube track. In order to return the pressure transmitter to service, it has been proposed to replace the existing tubing run. Drawing 33013-1250 Sh. 1 indicates this as ASME Class 3, and as such, is safety-related as described in Quality Control Manual section 2.1.14b.

The line specification for tubing requires that this be seamless, hand drawn copper, ASTM B75 type DHP, with .035 inch wall thick-ness, for up to 200 psig application. The proposed replacement is to be outside the tube track, eliminating the potential for a tube track contact problem and sharp bends.

B-280 3/8 inch copper tubing 'ith It fastened with tie-wrap to conduit in the area.

is proposed to use ASTM

.032 inch wall thickness, Per drawing C-381-358 Sht. 35, the tubing downstream of valve 4506 was not seismically analyzed, thus the temporary installation does not require to be seismically secured and will be retained through the use of tie wraps as indicated. As this is not a seismic installation the temporary tubing will be installed and supported in accordance with the requirements of ANSI B31.1-1986.

Stress experienced in the temporary line will consist of components due to pressure and sustained loads. The stress experienced from design pressure of the service water system is:

Sp = PDo = 150 si 0.375 in = 439 psi 4tn 4 (0.032 in)

The stress experienced from the sustained load of the tubing is:

Ss = 0.75i Mmax Where the maximum bending movement Mmax is determined from a maximum unsupported length of 36", thus Mmax equals; Mmax = Wx (L-X) = 0.086 lb in 36 in (36 in - 18 in) 2 2

= 28 in lb Thus Ss = 1 28 in lb = 10300 psi 0.0027 in and Stotal = Sp + Ss = 439 + 10300 = 10739 psi

91-20 The tensile strength of soft annealed ASTM B280 seamless copper tubing is 30,000 psi. Thus the temporary replacement of the original tubing with the above mentioned material will yield an acceptable factor of safety providing that the tubing is supported with tie wraps at a maximum of 36" intervals.

The above construction requirements are to be observed. Based on these, the determinations called for in 10CFR50.59 are given below.

The installation does not result in a change to the facility or procedures as described in the Safety Analysis Report because details involved with the support of the original tubing were not discussed or listed'nd this temporary installation alters only the physical configuration of the tubing.

The installation does not involve a change in the Plant Technical Specifications because the pressure transmitter PT 2028 is not a Tech Spec instrument and the connection is isolable from the service water system through valve 4506.

The installation does not increase the probability of an occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Safety Analysis Report because the installed tubing will be placed and run such that stress levels remain well below maximum values associated with the material; thus, the probability of failure o'f the replace-ment, temporary tubing will be no more than the original. Durati'on of the installation will be short term (approx. 2 months) thus probability of a failure is not effected.

The installation does not create the possibility for an accident or malfunction of a different type than any previously evaluated in the Safety Analysis Report because the replacement (temporary) tubing has been determined to be adequate for it's intended use and will be connected to the same isolation valve that would have isolated the original tubing run in the event of a failure (valve 4506) .

The installation does not reduce the margin of safety as defined in the basis for any Plant Technical Specification because the temporary installation will be adequately supported such that stress levels within the material do not 'xceed the tensile strength and thus under normal conditions no postulated failures are expected.

The design basis events analysis in the Safety Analysis Report which are associated with this proposed installation are the following:

Decrease in Reactor Coolant Inventory Seismic Events

.4 ~5.'Dl CATEGORY KLI'834$

REFERENCE PR OCEDURE,:

A 1402 REVIEWED

'OCHESTER GAS AND ELECTRIC GINNA STATION SYPASS OF SAFETY FUHG7iQN AND JUMPER CONTROL JOB FORE REQUEST 4:

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ENTERED IN OFFlCIALLOG; ENTERED IN OFFlCIAL LOG; NUMBEROFTAGSI NUMBER OF TAGS REMOVED:

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SHIFT SUPERVISOR ~sPn INSTALLATION REMOVAL DATES, TIME t I I DATE IIL TIME: t'NTERED ENTERED IN OFFICIAL LOG; IN OFFICIAL LOG; NUMBER OF TAGS INSTA NUMBER OF TAGS REMOVED:

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CATEGORY REFERENCE PROCEDURE A.1402 REVlEWc ROCHESTER GAS AND ELECTRIC GINNA STATION BYPASS OF SAFETY FUNCTION AND JUMPER CONTROL JOB FORBNN' P I <~ z r .< DATE REQUESTS:

JUMPER WIRE 0 LIFTED WIRE 0 FUSES PULLED 0 STATES BLOCK 0 OTHER/

FUNCTION ) V r u~i~

PURPOSE ul- o w AV Su~

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ENTERED IN OFFICIAL ENTERED IN OFFICIAL LOG:

LOG'UMBER OF TAGS INPPLLED: NUMBER OF TAGS RP4PVED:

INSTALLEDBY: REMOVED BY:

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/

FUNCTION Mo AoW PURPOSE Wo Cv' EOC 7a I Pi& 4-LOCATIO c ~ c v~I'CA. 0 c SP-SAFETY EVALUATIONREQUIRED: I YES 0 NO SKETCH ATTACHED: '0 YES D NO PORC DATE (IF REQUIRED)'ECHNICAL MANAGE DATE.

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1.0 Scope of Analysis The purpose of this analysis is to evaluate the safety consequences of connecting temporary recording equipment to Heat Trace Circuit E8P. This circuit has experienced erratic operation.

1 ' The following points will be monitored:

> Spare Contact on E8P Thermostat Controller

> E8P Thermocouple mV input 1.3 Per Procedure S-3.6, circuit E8P is heat trace for Boric Acid Pump gl, primary, Recorder 14A input point 18.

2.0 References 2.1 Ginna Procedure A-1406, Control of Temporary Modifications Ginna Station UFSAR, Sections 9.3.4.2.6 and 9.3.4.3.3.5 Ginna Station Technical Specifications, Section 3.2.3 2.4 Ginna Station Procedure S-3.6, Auxiliary Building Heat Tracing System Operation 3.0 Structures, Systems, and Components Affected (SSC)

There are no SSC's affected by this Temporary Modification. Since a spare contact will be utilized on the heat trace controller, the heat trace circuit will not be affected.

Since a recorder with an isolated, high impedance input will be used to monitor the thermocouple input, the controller input and Recorder 14A, point 18 will not be affected.

4.0 Safety Function of Affected SSC's 4.1 The Ginna Station UFSAR, in Section 9.3.4.2.6, addresses Heat Trace Systems associated with CVCS. This section does not specifically address heat trace associated with Boric Acid Pump g1.

Temp Mod 92-006 Page 1 02/28/92 Rev 0

The Ginna Station UFSAR, in Section 9.3.4.3.3.5, addresses the Boric Acid Transfer Pumps. This section does not specifically address heat trace associated with the pump.

4.3 The Ginna Station Technical Specification, in Section 3.2. 3 (b), addresses limiting conditions for operation regarding the Boric Acid Pumps.

Should Heat Trace Circuit ESP fail, Boric Acid Pump ¹1 may have to be declared inoperable. If it remains inoperable for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor must be brought to Hot Shutdown.

5.0 Effects on Safety 5.1 Heat trace associated with the Boric Acid Pumps inherently provides no direct safety function. Failure of heat trace on one pump is operationally covered by Technical

" 6.0 Specifications.

Connection of recording equipment .will not cause inadvertent failure of the heat trace circuit (see paragraph 3.0, above).

Unreviewed Safety Question Conclusions 6.1 The proposed temporary modification will not increase the -probability of occurrence of an accident previously evaluated in the UFSAR because this heat trace circuit does not directly provide an accident mitigating function.

6.2 The proposed temporary modification will not increase the probability or consequences of a malfunction of equipment important to safety previously evaluated in the UFSAR because this heat trace circuit does not directly provide a safety function.

6.3 The proposed temporary modification will not increase the consequences of an accident previously evaluated in the UFSAR because isolated recording techniques will be used and thus, will not cause heat trace controller failure.

Temp Mod 92-006 Page 2 02/28/92 Rev 0

The proposed temporary modification will not create the possibility of an accident or malfunction of equipment of a different type than any evaluated in the UFSAR because isolated recording techniques will be used and thus, will not cause heat trace controller or Boric Acid Pump failure.

6.5 The proposed temporary modification will not reduce any margin of safety as defined on the basis of any Technical Specification because isolated recording techniques will be used and thus, will not cause heat trace controller failure. Should the controller or heat trace fail during the troubleshooting period, causing Boric Acid Pump gl to be inoperable, Technical Specifications provide the criteria for taking. the reactor to shutdown.

7.0 Conclusion F 1 Based on the above discussion, the proposed temporary modification does not present an unreviewed safety question.

Temp Mod 92-004 Page 3 02/06/92 Rev 0

A-1406:13 TEMPOS MODIFICATION EVALUATION Part I coor nator)

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A-1406: 13 A T CHMEN TEMPORARY MODIFICATION EVALUATION Part I (TM Coor xnator)

TM No.: Date:

Title:

F PO Part II Inxtzator)

Type: Electrical Fluid Structural

==

Description:==

Fl a5 H ZTR~C'iiPC 7',

A<'Zz 8'b~oi C" ws88iw V~~ vs.

Part III (Station Engineer)

Design Inputs (i. e. Press, Temp, Corrosion, Hind, Seismic etc. )

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R'equirements:

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Safety Analysis: ttach documentation er A-303

~ ~

Mode Restrictions PREPARED BY: H DATE REVIEHED BY: DATE:

APPROVED BY: DATE: S /~ 2-PORC APPROVAL MEETING:

ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE ROCHESTER, NEW YORK 14649 GINNA STATION SAFETY ANALYSIS FOR TEMPORARY MODIFICATION REVISION 0 MARCH 11, 1992 TEMPORARY RIGGING TO REMOVE/INSTALL FIRE SYSTEM VALVE 9209 PREPARED BY:

Respons ble Staff Engineer REVIEWED BY Reactor Engineer Date REVIEWED BY:

Techni al Manager te APPROVED BY:

Chairman, Plant Operations Date Review Committee

1.0 S 0 0 ANALYSIS:

1~1 The purpose of this analysis is to evaluate the safety consequences of attaching temporary rigging to a structural member of the Turbine Building located above Fire Protection System valve 9209.

2 '

REFERENCES:

2 ' A-1406, Control of Temporary Modifications.

2 ' A-303 Preparation, Review and Approval of Safety Analysis for Minor Modifications for Special Tests.

2.3 Interoffice Correspondence, dated March 30, 1987, Subject AFCAR 86-12:RD Item g2 Anchorage of Temporary Equipment at Ginna Station, From L. Sucheski to J. Widay.

2 ' Technical Specifications Section 3.14.

3.0 STRUCTURES SYSTEMS AND COMPONENTS APPECTED SSC 3~1 Structures, systems and components affected directly or indirectly by the modification are as tabled below.

Structures ~sstems Com onents Turbine Bldg Fire Protection Valve 9209 4.0 SAFETY FUNCTION OR APRECTED SSCs 4~1 This area of the Turbine Building presently serves no safety function. It's primary purpose is to provide protection of 'secondary plant equipment.

4 ' The Fire Protection System and valve 9209 aie classified as Safety Significant. Their safety function is to provide a supply of water for Fire Protection.

Safety Analysis Page 1 Revision 0

~92-00

EPPECTS This temporary modification will not adversely affect any other components or equipment with any safety functions. This temporary modification will not adversely affect the Turbine Building, as it serves no safety function. This temporary modification will not adversely affect the Fire Protection System, as this portion of the system will be taken out of service for maintenance of valve 9209. The temporary modification will in turn be removed when maintenance is completed and can thus not affect. the inservice Fire Protection System.

6.0 UNREVISED SAPETY UESTION CONCLUSIONS 6.1 The proposed modification will not increase the probability of occurrence of an accident previously evaluated in the UFSAR. Only the structure of the Turbine Building and the out of service portion of the Fire Protection System will be affected and other surrounding equipment is not utilized for any accidents

" evaluated in the UFSAR.

The proposed modification will not increase consequences of an accident previously evaluated in the UFSAR because only the Turbine Building structure and the out of service portion of the Fire Protection the System vill be affected.

6 ' The proposed modification vill not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the UFSAR because only the Turbine Building structure and the out of service portion of the Fire Protection System will be affected.

6 ' The proposed modification will not increase the con-sequences of a malfunction of equipment important to safety previously evaluated in the UFSAR because only the Turbine Building structure and the out of service portion of the Fire Protection System will be affected.

6.5 The proposed modification will not create a possibility for an accident of a different type than any evaluated previously in the UFSAR because only the Turbine Building structure and the out of service portion of the Fire Protection System will be affected and the

'rements of Technical Specifications have been dered.

Safety Analysis Page 2 Revision 0 92-009

6.6 The proposed modification will not create a possibility for a malfunction of equipment of a different type than any evaluated previously in the UFSAR because this modification only affects the Turbine Building structure and the out of service portion of the Fire Protection System.

6.7 The proposed modification will not, reduce any margin of safety as defined in the basis of any Technical Specifi-cation because only the Turbine Building structure and the out of service portion of the Fire Protection System is affected, the temporary modification will be removed and the system restore to service following maintenance of the valve.

7.0 CONCLUSION

7~1 This modification does not involve an unreviewed safety question based upon the discussion contained w'ithin this document.

Safety Analysis Page tRevision 3 0 92-009

ATTACHMENT 1 TEMPORARY MODZPZCATZON EVALVATZON PART Z

, TM No: 92-010 Date: 03 23 92 Rev. 0

Title:

INSTALL "A" MFP SEAL DP TRANS I TE AND RECORDER PART ZZ Types Electrical x Plui.d ~ Structural

Description:

IN ORDER TO MONITOR MFP S L D D ING SHUTDOWN AND START UP INSTALL A TEMPORARY RANSMITTER TUBING AND THREE WAY BLOCK VALVE DOWN STREAM OF ROOT VALVES 3810B AND 3810C FOR PS-2051 MFP SEAL DP PRESSURE SWITC ALSO NST LL A TEMPORARY WI E FROM THE OUTPUT OF PT-201S "A" FP SUC ON P ESSURE AT TEST POINT TP-6 LOCATED IN THE LOCAL FEEDW TER P EL. HE OUTPUT FROM THE SEAL DP TRANSMITTER AND T E W F 0 -6 WILL BE INPUT TO A GOULD RECORDER LOCATED TH E D P ROOM NEXT TO THE FEEDWATER CONTROL PANEL. POW OR CORDER AND HE NEW T WILL BE SUPPLIED FRO 20V C W SO D TION WHILE THE TRANSMITTER IS BEING F LLE V NT D MFP LOW SEAL DP WILL BE DEFEATED See Attached Sketch 1 and marked u dw s 33013-1905 1627 1959 for detai s PART ZZZ Design Inputs: Sealwater In'ection desi n ressure: 400 si Sealwater In'ection des' tern erature: 375 F Fluid: Condensate wate Code: ANSI B31.1 1986 Evaluation: MECHANICAL- Tub n sha be seamless stainless steal fittin ts e 304 SS t A

or 316 and e 316 or 304.

fitt' shal be swa e ok com ression his mee s the s stem tern erature ressure and code desi n cond'tions er Gilbert line s ec SP-863

-1.The valves for the new tra sm tte s a e A derso Greenwood Ass No. 25-257-540 t e 1HS3TON. his is a T e 3 6 SS three wa i strument block valve wit a 00 the s stem code tern eratu e S

ess e des at . This meets e 'ments.

The new transmitter shall be osemou mode tra smitter 's made f o 3 6 S a t ode s rate S 22B1. This o 2500 si worki ressure. his als'o meets s ste des e erne ts. T e new tra smitter will be i idl mou ted su ort to the new tubin and valves. Tem erature affects on the ovide ade uate page 1 of 3

TEMPORARY MODIFICATION 92-010 Evaluation (cont.)

new tubin is not a consideration since essentiall the tubin will be at ambient is tern erature sufficient due to flexibilit no flow thou h the new

~tubin and there in the tubin run to accommodate an thermal ex ansion. Sketch 1 rovides the necessar installation instructions.

B ELECTRICAL- A tern orar wire will be connected at test oint TP-6 reference RG&E dw 33013-1627 within the Feedwater anel located in the MFP room and in ut into the tern o a Gould recorder also located in the MFP room. Since TP-6 is an established test oint and the Gould model 22005 has isolated in uts control circuits will not be affected b an cable faults. The addition of the Rosemount DP transmitter will onl in ut to the Gould recorder and conse uentl will also not affect control circuits.

In order to revent an false low seal DP si nals from tri in the "A" MFP while the new transmitter. tubin is bein filled and ve ted the DP si nal will be b assed unt'l the new transmitter is in service. This will be accom lished b o enin the states deck for terminals 1 and 2 on terminal block FL-2 located in rela rack RA-2 front for the contact from rela AR-58 which closes to make u the "A" MFP tri circuit. This will revent the AR-58 contact in the MFP tri circuit from closin and ener izin the tri coil. Rela AR-58 is deener ized when PS-2051 is closed which then closes contact AR-58 in the um tri circuits. see attached drawin s 33013-1959 shl 10905-0030A sh1 and 10905-318 for reference C OPERATIONS- As a com ensator measure while the low seal DP is defeated an Auxiliar 0 erator shall be stationed locall to monitor "A" MFP seal DP.

Testing Requirements: The new tubin valve and transmitter connections shall be checked for leaka e rior to reinstatin low MFP seal DP tri 8afety Review: See attached safet evaluation for TM 92-010 Design Review: The Desi n Review Checklist er A-304 has been considered and all a licable items have been addressed satisfactoril met.

Mode Restriction: None page 2 of 3

TEMPORARY MODIFICATION 92-010 Evaluation (cont.)

PREPARED BY DATE!

REVIEWED BY: DATg: 3/ z Y/f K REVIEWED BY DATE! ~ ~V ~o APPROVED BY DATE PORC APPROVAL MEETING. Is~ v DATE, Z5 page 3 of 3

SAFETY ANALYSXS Temporary Connection of a Pressure Transmitter to <<A<< MFP Seal Differential Pressure Switch and Temporary Defeat of Low Seal DP MFP Trip Ginna Station Rochester Gas and Electric Corporation 89 East Ave Rochester, New York 14649 TEMPORARY MODI'FICATZON 92-010 Rev. 0 March 23, 1992 Prepared by: >go/rz Sta f gi e Date Reviewed by:

Reactor Engineer Date Reviewed by: 3 ~vz-Manager Tec ical Eng'ering Da e Approved by:

Chairman, Plant Op rations Review Committee at

1.0 Scope of Analysis The purpose of this analysis is to evaluate the safety consequences of temporarily connecting a pressure transmitter across the "A" main feed water pump (MFP) seal injection differential pressure (DP) switch PS-2051.

1.2 In addition, the affects of temporarily defeating the "A" MFP low seal DP pump trip while filling and venting the new transmitter will also be evaluated.

1.3 The safety consequences of temporarily connecting a recorder to test point 6 in the feed water panel has already been reviewed under TSR 92-057 and found to be acceptable.

Therefor'e, this analysis will not address the recorder 2.0 References F 1 Plant Procedure A-1406, Control of Temporary Modifications 2 ' Ginna UFSAR sections 10.4.4, 10.4.5, 15.2.6 2.3 Temporary Modification 92-010 Structures, Systems, and Components Affected (SSC)

, 3.0 The "A" Main Feed Water Pump is affected by this Temporary modification 4.0 Safety Function of Affected SSC's 4.1 The MFP does not perform any safety functions 4 ' The function of the low seal DP trip is solely to prevent pump seal damage due to loss of cooling. Zt does not provide any safety functions 5.0 Effects on Safety 5.1 The purpose of adding a pressure transmitter to the seal pressure switch is to record pressure transients during unit shutdown and start up. On several occasions during. pressure transients associated with start up and shutdown of the feed water system low seal DP trips have occurred on the "A" MFP.

Having a hard copy of the transients may provide information which could attribute the pressure fluctuations to equipment manipulations.

Safety Analysis Rev. 0 Temp Mod 92-010 Page 1 03/23/92

5.2 Per the Temporary Modification Evaluation, all the new tubing, fittings, valves, and the transmitter meet the design requirements for temperature and pressure for the Seal Water Injection system. In addition the new components will be properly supported to prevent any structural damage.

5.3 As a precautionary measure, while the new equipment is being filled and vented, the low seal DP to the "A" MFP will be defeated to preclude any false signals. As a compensatory measure, local indication will be monitored to alert the operators to any real low DP signals. These measures will prevent any spurious or false loss of feed water.

6.0 Unreviewed Safety Question Conclusions 6.1 The proposed modification will not increase the probability of occurrence of an accident previously evaluated in the UFSAR because the new equipment meets all the system design requirements and during installation measures will be provided to prevent any false pump trip signals that could result in a partial loss of feed water.

6.2 The proposed modification will pot increase the consequences of an accident previously evaluated in the UFSAR because Auxiliary Feedwater is unaffected by this modification and it provides the safety function. for a loss of main feedwater.

6.3 The proposed modification will not increase the probability or consequences of a malfunction of equipment important to safety previously evaluated in the UFSAR because any potential false signals from during installation of this modification will be defeated and direct continuous operator monitoring will be provide the pump protection function.

6.4 The proposed modification will not create the possibility of an accident or malfunction of equipment of a different type than any evaluated in the UFSAR because the feed water system function and design will not be changed.

6.5 The proposed modification will not reduce any margin of safety as defined in the basis of any Technical Specification because the main feed water pumps are not part of Technical Specifications nor are they part of any of the basis.

7.0 Conclusion Based on the above discussion the proposed modification does not present an unreviewed safety question.

Safety Analysis Rev. 0 Temp Mod 92-010 Page 2 03/23/92

TECHNICAL RECORD/

Category TEMPORARY MODIFICATION EVALUATION PART I TM No: 92-011 Date: ~03 26 92 Rev. 0

Title:

TEMPORARY CHILLER SYSTEM PART II Type: Electrical x Fluid x Structural e ~ i

==

Description:==

See Attached

'ART ZZI Design Inputs: Service Water des' ressure: 150 si desi n tern erature: 200 F luid: Lake water Code: ANSI B31.1 1955 Chil ed Water desi ressure: 75 n tern erature: 100 F s'esi Flu'd: Gl col and Water Code : ANSI B31.1 1955 Evaluation: See attachement 1 Testing Recpxirements: The new hoses valves and ithein s connections shall be checked for leaka e rior to o eratin stem.

Safety Review: See attached safet evaluation for TM 92-011 Design Review: The Desi n Review Checklist er A-304 has been considered and all a licable items have been sat'sfactoril met.

Mode Restriction: None Page 1 of 2

TEMPORARY MODIFICATION 92-011 PREPARED BY: DATE: 3 >7 <>

REVIEWED BY DATE: 2 iS APPROVED BY: DATE:

PORC APPROVAL MEETING DATE page 2 of 2

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pt7 ~abF&EA37 TEMPORARY SYSTEM Qg~ /sP 7 CHILLED WATER DESCRIPTION:

The Chilled Water System provides cooling for the control room. Heated air and cooled air are mixed in proper proportions with dampers to maintain a comfortable air temperature.

The purpose of this temporary system. is to maintain chilled water primarily to the control room and secondarily to the sevice building HVAC systems while the Chilled Water heat exchangers (SCI03A and B) are removed from service for maintenance. Chilled Water will be cooled by Service Water th roug h temporary e redundant heat exchangers and recirculated by temporary pumps. Each heat exchanger zs capa ble of removing enough heat to service the control room.

Only the chilled water will be effected, air balances and filtration will remain unchanged from the normal HVAC configuration.

1.5" hoses will be connected between Service Water and the tube side of each heatexchanger. The service water system has ample capacity to supply this flow. Chilled Water will be routed from drain valves on the return header (valves 5836A and 5836B) to the suction side of two pumps with temporary piping. The discharge from these pumps will be routed to the se side of the heat exchangers. The shell side outlets wil s'ell be routed to the Chilled Water supply header (valves 5834B an d 5634C), closing the loop.

The hot and cold deck controllers will function normally and ~

can be adjusted to maintain a level comfort in the Control Room. Other Chilled Water loads will be supported but. can be isolated or throttled the Control Room.

if necessary to support. the demand of DESIGN CRITERIA:

The function of the Control Room HVAC System is to provide a controlled environment for the safety and comfort of .the control room personnel and to ensure the operability of the control room components during normal operating, anticipated operational transient, and design basis accident conditions.

ALCULATXON-'=MCph,T where:

g=hea C-Cransf er

, M=flowraCe Cp=speci fic-hea C AT= tempera tur e-change (100GPM) (1 BTU/LB F) (10 F) (8 LB/GAL) (60 MIN/HR) = 480~000 BTU/HR Water flov through the temporary chill vater system is limited by the pressure drops, 50 GPM is expected for each of the two loops, or a total of 100 GPM.

The Temperature of the Service Water (Lake Ontario Temperature) is typically less than 40 deg for this time of year.

The Service Water or a total of 200 flov rate GPM.

vill be 100 GPM per heat exchanger The Chilled Water delta T desired is 10 deg for a total heat transfer rate of 480,000 BTU/HR (both heat exchangers). the Service Water temperature will increase 5 deg for this heat transfer.

The control room heat load was found to be 48,700 BTU/H as reported in the Devonrue Environmental Study. The estimated heat transfer rate of this temporary system is adequate .to maintain a level of comfort in the control room. Excess cooling capacity vill be used by the service building HVAC units.

EVALUATION:

Maintaining the control room safety and comfort is the safety significant function of the control room HVAC system. This temporary system will remove the heat necessary to maintain the level of comfort in the control room.

This system is made up of redundant independent heat exchangers and pumps. If any single component should fail, the redundant system is capable of supplying the control room HVAC cooling.

In the loss of Service Hat as no new condition introduc , anent system also uses SW as

~the al heat sa ever, fire e heat sink for the temporary is available as an In the case of the loss of offsite power the chiller system is powered by.)us 13 and 15 which %emptied to safeguards busses but ~~be automatically disconnected for diesel loading conditions. An alternative power supply could be obtained within a matter of hours for the temporary pump(s).

If a temporary heat exchanger toshould building drains are adequateschizo leak, the turbine prevent flooding. The Service Hater and Chilled Hater Systems are both rated at 150 psi and do not pose an over pressurization question should there be a tube to shell leak. Normal make up to the chilled water system will remain in service preventing a loss of inventory. The maximum head of the temporary pumps is well below the design pressurera>~4 of the&. $piping. Ffre Hose- lY>

/pe, Qm p5( ocv( QVc PtPE Q pQg. 7><<F The two Systems in question are not high energy, and a break in the temporary piping does not represent a safety hazard to personnel in the area.

I The structural loads introduced by this temporary system are minor, the majority of the weight will be supported by the turbine building basement concrete floor. Each pump, heat exchanger and associated piping (excluding fire hose) will weigh less than 280 pounds full of water.

temporary system does not pose an aewed safety question. t does not increase the a ility of occurrence of an acciden malfunctio equipment. important to safety

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SAFETY ANALYSIS Temporary Chiller System Ginna Station Rochester Gas and Electric Corporation 89 East Ave Rochester, New York 14649 TEMPORARY MODIFICATION 92-011 Rev. 0 March 26, 1992 Prepared by:

Staff Engineer Date Reviewed by: D 28 'Fz React En ineer D te Reviewed by: '3 Z Manager, Tech 'cal ngineering at Approved by:

Chairman, Plant Operations Review Committee at

'emporaryScope of Analysis Chiller System The purpose of this analysis is to evaluate the safety consequences of temporarily connecting a chiller system for the Control Room HVAC system while Service water valves and Chiller valves are being replaced in the permanent system.

The system will be connected for approximately one week.

,2.0 References .

F 1 Plant Procedure A-1406, Control of Temporary Modifications 2' Ginna UFSAR sections 6.4, 9.4.3 2.3 Temporary Modification 92-011 2.4 Ginna Technical Specifications sections 3.3.5, 3.5.6 2.5 Devonrue Environmental Study 3.0 Structures, Systems, and Components Affected (SSC)

The Chilled Hater System will be af fected by this temporary modification. The chiller system provides cooling to the trol room and service building HVAC units. The Chiller system is a closed loop system cooled by Service through two 1004 capacity redundant heat exchangers and pumps 4.0 Safety Function of Affected SSC's 4.1 Xn the event of a design basis accident, the Control Room ventilation system provides sufficient radiation protection, ventilation, filtering and Toxic gas detection to ensure that control room personnel can perform all required safe y functions from the Control Room.

4' Although Control Boom cooling is not required by the Technical Specifications, under certain limiting Control Room heat load and outside air temperature conditions, the chillers are required to maintain Control Room temperature within design limits. ( ref 2.5) 5.0 Effects on Safety 5 ' The Control Room chiller system is a commercial grade non-safety related non-class 1E system and is not required by the control room HVAC system to perform safety function 4.1.

Safety Analysis Rev. 0 Temp Mod 92-011 Page 1 03/26/92

'emporaryThe chiller system is a Chiller System safety signif icant system. Conseque-ntly, the temporary system will be provided with redundant pumps and heat exchange& powered from bus 13 and 15 similar to the permanent chiller system. Service water cooling will be supplied with fire hoses from the Turbine Building header. The Turbine building Header has supply connections from both Service water headers similar to the Intermediate building header which supplies the permanent Chiller system.

The temporary system meets both the Service water and the Chilled water syst: em pressure and temperature requirements.

5.3 This temporary system provides redundant chiller capacity sufficient to remove heat from Control Room loads. According to the temporary modification evaluation (ref 2.3), the temporary system with both heat exchangers operating will provide approximately 1/3 ( 480,000 BTU/HR ) the capacity of the existing system. Based on test data, reference 2.5, the 1004 power heat load for the Control Room is approximately 49,000 BTU/HR. The remainder of the heat load is from the service building.

5.4 Due to the weather conditions during the months of March and April and the reduced heat loads as a result of shutdown, this is considered sufficient capacity to prevent elevated temperatures in both areas. However, should temperatures increase in the Control Room, cooling flow to the Service building will be throttled .or isolated. This will ensure that as a minimum, the control room will have sufficient. cooling.

Previous operational history during shutdowns with the chiller system totally isolated for short duration did not cause any appreciable Control Room heat up.

5.5 Should any leaks develop in either the temporary SW or Chiller piping/hoses, the associated volumes are enveloped by a break in the 36" Circulating Water piping. No water spray hazards will be introduced since the temporary hoses will not be routed in the area of any safegaurds buses.

6.0 Unreviewed Safety Question Conclusions 6.1 The proposed modification will not increase the probability of occurrence of an accident previously evaluated in the UFSAR because replacement of the permanent commercial grade Chilled Water system with the redundant loop temporary system does not reduce the margins of safety.

Safety Analysis Rev. 0 Temp Mod 92-011 Page 2 03/26/92

ATTACHMENT TEMPORARY MODIPICATXON EVALUATION PART I o>l oq Jnz.

TM No: 92-029 !I

Title:

Disable CET's A-7, B-5, C-8, G-4, H-13, K-3 >

-a~97C. L.-JO PART II Type: Electri.cal

Description:

Intermittent and/or fai.led CET's are causi.ng spurious alarms, erroneous indication, or failed indication. Disable CET inputs, as listed above, at Incore Rack $ 4 as follows:

A-7 T2B Terminals 5/6 B-5 T2A Terminals 3/4 C-8: T1B Terminals 2 1/22

- G-4:

H-13:

K-3 T1B T1A T1B Terminals Terminals Terminals 3 1/32 23/24 5/6 g-~O i IA i CEI IVloh~h 6 9/)o PART II1 Design Inputs: RGE Drawing 33013-1569 WR/TR 9200911 UFSAR Table 7.5-1, Note 2 UFSAR Section 7.7.2.6.4.5 Technical Speci.fication Table 3.5-3 Evaluation: Ginna Technical Specifications require a minimum of four CET channels per core quadrant to be operable. The Ginna UFSAR indicates that one core map per hour is generated and stored in he Plant Process Computer System (PPCS). Disabling the above CET's will not affect Technical Specification compliance or create an unreviewgp safety configuration. As the attached sketch indicates, more th@N four CET's per quadrant remain available and the disabled CET's will not affect PPCS mapping. 76s~ 4aYi'~o <<<

prov& r'cpD r'c ~~ < <r~4'4~5.

Testing Recpxi.rements: Ensure that the remaining CET's are operating normally.

Safety Review: Refer to attached Safety Evaluation.

Design Review: All the applicable items in Figure 1 of A-304 have been adequately addressed and no other issues are of concern.

Mode Restriction: None TE.

PORC APPROVAL MEETING DATE. / d PicPmec g g~ . X~ 7c l4ui e~ gg

~ I +p~ y~g Po a.c P~p~y~ ~< ~g~ (o /5

ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE ROCHESTER, NEW YORK 14649 GINNA STATION SAFETY EVALUATION FOR TEMPORARY MODIFICATION 92-029 REVISION 0 JULY 9, 1992 DISABLE CORE EXIT THERMOCOUPLES PREPARED BY Respon able Staff Engineer Date REVIEWED BY:

Reactor Engineer Date REVIEWED BY:

Technical Manager ate APPROVED BY: 7/5 hairman, Plant Operations ate Review Committee

DISABLE CORE EXIT THERMOCOUPLES SAFETY ANALYSIS 1.0 SCOPE OF ANALYSTS This purpose of this analysis is to evaluate the safety consequences of temporarily disabling up to all but four Core Exit Thermocouples (CET's) per quadrant with the exception that RVLIS CET's in locations E-6, F-8, G-7, H-6, J-8 and J-9 will not be disabled.

1.2 The thermocouples are typically disabled due to the production of erroneous indication leading to spurious alarms or basic thermocouple failure.

2 0 REFERENCES 2~1 A-1406, Control of Temporary Modifications.

2 2 A-303, Preparation, Review and Approval of Safety Analysis.

2' Ginna Station UFSAR, Sections 7.3.2. 3, 7. 6.5, 7.7.2. 6.4.5 and Table 7.5-1, Note 2.

2.4 RG&E Drawing 33013-1569.

2 ' Ginna Station Technical Specifications, Table 3.5-3.

3 ' STRUCTlJRES SYS EMS AND COMPONENTS AFFECTED SSC 3~1 Mapping overall core temperature will be affected slightly by disabling up to all but four thermocouples per quadrant. As long as a minimum of four thermocouples per quadrant remain, each quadrant will be adequately monitored for temperature.

4.0 SAFETY FUNCTION OF AFFECTED SSCs 4 1 The CET's are positioned to measure fuel assembly coolant temperatures at preselected core locations for the purposes of mapping and for input to the RVLIS.

4.2 The Ginna Station UFSAR indicates that. one core map per hour is generated and stored in the Plant Process Computer System (PPCS). Disabling all but four CET's Safety Analysis Page 1 Revision 0 Temp Mod 92-029

will have a minimal affect on this mapping.

4.3 The Ginna Station Technical Specifications require a minimum of four CET channels per core quadrant to be operable and for two channels of the RVLIS to be operable. Disabling all but four CET's per core quadrant and ensuring that the RVLgp CET's as indicated in Section 1.1 are not disabled~hot affect Technical Specification compliance.

5.0 EFFECTS ON SAFETX 5.1 Per Section 4.0, no effect on plant safety is anticipated.

6.0 UlGU.VIEWED SAFETX UESTION CONCLUSIONS 6.1 The proposed Temporary Modification will not increase the probability of occurrence of an accident previously evaluated in the UFSAR because overall core temperature will still be adequately monitored.

6 ' The proposed Temporary Modification will not increase the consequences of an accident previously evaluated in the UFSAR because the CET system will be minimally affected and the RVLIS system will be unaffected.

6.3 The proposed Temporary Modification will not increase the probability of occurrence of a malfunction of equipment important, to safety previously evaluated in the UFSAR.

No othex equipment important to safety is affected by this temporary modification to the CET system (other than core tempexature monitoring) because the CET's required for the RVLIS will not be disabled.

6.4 The proposed Temporary Modification will not incxease the consequences of a malfunction of equipment important to safety previously evaluated in the UFSAR. No other equipment important to safety is affected by this temporary modification to the CET system (other than core temperature monitoring) because the CET's required for the RVLIS will not be disabled.

6.5 The proposed modification will not create a possibility for an accident of a different type than any evaluated previously in the UFSAR. No equipment is affected by this temporary modification to the CET system (other than core temperature monitoring) due to the requirement that the CET's for the RVLIS will not be disabled.

Safety Analy'sis Temp Mod 92-029 Page 2 tRevision 0

6.6 The proposed Temporary Modification will not create a possibility for a malfunction of equipment of a different type than any evaluated previously in the UFSAR because this installation has been shown to not impact any equipment important to safety.

6.7 The proposed Temporary Modification will not reduce the margin of safety as defined in the basis of any Technical Specification. Each core quadrant will be adequately monitored by a minimum of four CET's. In addition, CET's required for the RVLIS will not be disabled.

7.0 CONCLUSION

7.1 Based on the above analysis, the proposed Temporary Modification does not present, an unreviewed safety question.

Safety Analysis Page 3 Revision 0 Temp Mod 92-029

ATTACHMENT 3.

TEMPORARY MODZRZCATZON EVALUATZON PART X TM No: 92-045  : ~EP iilit/02 TITLE: AOV-9553B AVT Rinse Drain Valve Replacement Cfk PART XI Type: El ectrical Fluid I Structural

Description:

Due to AOV-9553B leaking through, a temporary manual drain valve has been installed. The AOV was replaced with a 4 inch flange with a 2 inch pipe and valve. When an appropriate replacement valve is available, the temporary valve will be removed.

XII

. PART Design Xnputs:

Line Spec 300-1; per DWG 33013-1911 Shtl; Condensate pump dis-charge: Design Pressure = 400 psig, design Temp = 150 Deg F Operating Pressure = 300 psig, Operating Temp = 100 Deg F Valve =

Crane valve catalog HARPpal w egal, gag~

This installation is non-QA, non-Seismic, non-Safety Class and non-'ASME Code Class.

Evaluation:

The AVT system was a vendor"supplied system and specific design conditions are not readily available. However, the interfacing Condensate system design parameters envelope the AVT system, consequently,, the Condensate Pump suction operating conditions will be used. During normal operation, valve 9553B is isolated via upstream valves from each vessel, consequently, it. does not see normal condensate pressure. During operation of the flushing cycle there is a pressure reducing orifice upstream of drain valve 9553B. As such, the drain valve does not experience the 300 w

this application. ZOO~

~ a Testing Requirements:

None Safety Review:

See PCN 91T-1254 for procedure T-6.1 Design Review:

The design review checklist, per A-304, has been reviewed and all applicable items have been met.

Mode Restriction:

None ATES PORC APPROVAL MEETING. /~S '0 s /"/8- DATE /

Preparal Sg:

Rc vie~eg Qg; Agan uch LAN i~

ATTACHMENT TEMPORARY MODXPXCATXON EVALUATION PART I TM No: 92-045 Date: 06/04/92 .

Rev: 0 TITLE: AOV-9553B AVT Rinse Drain Valve Replacement PART II Type: Electrical Fluid X Structural

Description:

Due to AOV-9553B leaking through, a temporary manual drain valve has been installed. The AOV was replaced with a 4 inch flange with a 2 inch pipe and valve. When an appropriate replacement valve is available, the temporary valve will be removed.

PART IXX Design Inputs:

Line Spec 300-1; per DWG 33013-1911 Shtl; Condensate pump dis-charge: Design Pressure = 400 psig, design Temp = 150 Deg F Operating Pressure = 300 psig, Operating Temp = 100 Deg F Valve = Lunkenheimer 150 S, 300 WOG Crane valve catalog This installation is non-QA, non-Seismic, non-Safety Class and non-ASME Code Class.

Evaluation:

The AVT system was a vendor supplied system and specific design conditions are not readily available. However, the interfacing Condensate system design parameters envelope the AVT system, consequently, the Condensate Pump suction operating conditions will be used. During normal operation, valve 9553B is isolated via upstream valves from each vessel, consequently, normal condensate pressure. During operation it of does not see the flushing cycle there is a pressure reducing orifice upstream of drain valve 9553B. As such, the drain valve does not experience the 300 p si g p ressure and the 300 WOG rating is considered adequate for this application.

(

. Testing Regnirements:

'I

None Safety Review:

See PCN 91T-1254 for procedure. T-6.1 Design Review:

The design review checklist, per A-304, has been reviewed and all applicable items have been met.

Mode Restriction:

None PREPARED BY REVIEWED BY DATE APPROVED BY DATE PORC APPROVAL MEETING 8S0 s /-/8 DATE: /

SECTION E - PROCEDURE CHANGES This section is to contain a description of the changes to procedures as described in the UFSAR and a summary of the safety evaluation pursuant to the requirements of 10 CFR 50.59(b).

PROCEDURE DATE PCN 8 jc 8 Items 1, 2, or 6 If "yes" is answered "inconsenuential for Ztems 1 or 2, provide the type of change" or the referenced locFR50.59 safety evaluation below:

Change Type:

Zf "no" was answered for Item 6, provide the basis for exclusion below:

Basis for Exclusion:

OC 0 va u - Item 7 If "no" has this change been answered for each question in items 7a through 7g is not an Unreviewed Safety Question. Document the

)ustification for these conclusions below. List any material referencer'. in the space provided. err~,'r written Justification:

ES'8 w r'2 cP uA'Z-Refe e so-s-S Zf "yes" was answered for Item 3, check this box If "yes", was answered for Item PORC this submittal. This proposed 7,change shall review and approve ia an Unreviewed Safety Question (USQ) and requires submittal to the NRC f'r their review.

Submitted By:

ROCHESTER GAS AND ELECTRIC CORPORATION Inter-Office Correspondence February 6, 1992

SUBJECT:

Axial Repositioning of the Control Banks A and B Safety Evaluation per 10CFR50.59 TO: PORC On October 16, 1991, by meeting f91-135, PORC approved the safety evaluation for repositioning the Shutdown Bank of rods to 227. The basis for this approval was that with 227 steps withdrawn remaining above the active fuel region, the reactivity effect of the change in bank position was negligible. This was confirmed during repositioning from observing no change in either RCS temperature or axial flux distribution.

The purpose of this evaluation is to address the repositioning of the Control Banks A and B to 228 and 229 steps respectively as the fully withdrawn position. This would be effective with startup following the 1992 outage and would result with the full out positions for each bank as follows:

Shutdown Bank 227 Control Bank A 228 Control Bank B 229 Control Bank C 230 Control Bank D 230

~

Therefore, with the normal rotation of RCCA's between banks that results with each refueling, the wear locations on the rodlets would be different each year.

As discussed for the Shutdown Bank and observed during repositioning, the reactivity effect of the change in the fully withdrawn position for CB's A and B will have no effect on shutdown margin and power distribution. Therefore there will be no affect on the design basis events of rod ejection, uncontrolled rod withdrawal or dropped rod.

Technical Specification 3.10.1.3 requires that the control bank position satisfy the insertion limit curves of TS Figure 3.10-1 and that the banks move sequentially with a 100 (+5) step overlap.

Figure 3.10-1 shows rod position in terms of percent withdr-awn. Similar to the interpretation of "fully withdrawn" for the shutdown bank, Nuclear Safety and Licensing interprets the 100 withdrawn as not inconsistent with the position of 228 or higher.

The bank overlap unit is currently set to begin withdrawal

of a control bank when the preceding bank is at 130 steps. The 100 step overlap is from 130 to 230 steps. It is proposed that this 130 step position for initiation of overlap not be changed, but that the A and B bank position for stopping withdrawal be set at 228 and 229. Since there is no reactivity worth from 228 to 230,. this change will have. no effect on the combined reactivity worth per step for both banks moving sequentially and therefore no effect on power distribution or control. Also, the 2 step variation from the 100 step overlap is within the variance of +5 steps allowed by Technical specifications.

This proposed change to the 100 percent withdrawn position for Control Banks A and B has been evaluated in accordance with the criteria of 10CFR50.59. This change does not present an unreviewed safety question for the following reasons:

The probability of occurrence or the consequences of an accident previously evaluated in the UFSAR will not be increased.

The repositioning of the control banks will have no reactivity effect due to the rods remaining above the active fuel region in the proposed full withdrawn position. This was confirmed during the repositioning of the Shutdown Bank where no effect on RCS temperature or axial flux distribution was observed. Since the rod position for initiation of succeeding bank withdrawal will not be changed (130 steps),

there will be no change to the combined reactivity worth per step for rods moving in sequence and overlap. Therefore there will be no change in the rodded power distribution during withdrawal and the basis for the Technical Specifica-tion is satisfied.

Adjusting the thumbwheel switches (S2 and S4) in the bank overlap unit to terminate movement of CB A and B at 228 and 229 respectively will have no effect on the probability of occurrence of a uncontrolled rod withdrawal, rod ejection or rod drop. Since there is no reactivity effect of lower position of Bank A and B, there can be no affect on the consequences of these events.

The probability of occurrence, or the consequences of a malfunction of equipment important to safety will not be affected.

As discussed above, adjusting the thumbwheel switches on the bank overlap unit will have no effect on the probability of a malfunction of the rod control system. This adjustment the unit in a configuration not originally will not placediscussed intended. As above there will be no affect on the consequences of a rod control system malfunction.

The possibility of an accident or malfunctionUFSAR of equipment of a different type than any evaluated in the will not be created.

Repositioning the fully withdrawntheposition of Control Bank A and B will have no effect on rod control or reactor protection systems.

The margin of safety as defined in the basis for any technical specification will not be reduced.

As discussed above, by maintaining the bank position at which succeeding bank withdrawal is initiated (130 steps),

there will be no effect on the combined reactivity worth per step or the power distribution. Therefore the margin of safety as defined in the basis for any Technical Specification is not reduced.

John . Cook Reactor Engineer xc: Steve Adams Jeff Wayland

SECTION F COMPLETED SPECIAL TESTS (ST) AND EXPERIMENTS This section is to contain a description of special tests and experiments performed in the facility, pursuant to the require-ments of 10 CFR 50.59(b). Within the time frame of this report, there were none conducted.

CONCLUSIONS:

All of the above were reviewed by the PORC committee with respect to the Technical Specifications and the committee has determined that no Technical Specification changes or violations were involved.

Additionally, these changes were reviewed in committee to determine if they presented an Unreviewed Safety Question and the general summations of these reviews are as follows:

These changes do not increase the probability of occurrence, or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the UFSAR, because:

These changes were performed to ensure continued operability/

availability of plant equipment and will not result in any equipment being operated outside of its normal operating range. This results in continued operability/availability of equipment important to safety. These changes additionally will not result in a change of operating characteristics of equipment used in the transient/accident mitigation which precludes an increase in the probability of occurrence of an accident. Because these changes ensure continued availability of plant equipment, the limits shown in the Technical Specifications, and the assumptions of the safety analyses of the Updated Final Safety Analysis Report continue to be met. As a result there is no increase in the consequences of any presently postulated accident.

2 ~ These chan'ges do not create the possibility for a new or different kind of accident, or a malfunction of a different type from any accident previously evaluated in the UFSAR because:

The changes do not present new failure mechanisms outside of those presently anticipated, and are bounded by the events contained in the Updated Final Safety Analysis Report.

3 ~ The changes do not reduce the margin of safety because:

Present margins as contained in the Technical Specifications are valid, and these changes are performed within those limits. These changes will not result in violating the baseline assumptions made for equipment availability in the Technical Specifications, and the Updated Final Safety Analysis Report.

A-1406 13 ATTACHMENT 1 TEMPORARY MODIFICATION EVALUATION Part I (TM Coordinator)

No.-' D~ ~ Date: /2 TM

Title:

r Ci rf'hyme Part II (Instigator)

TYpe: Electrical Fluid Structural

==

Description:==

iAd +: ~PC'e uir ureA(

Sdd l9 ~~c T glpcu( g/~

chccLut 80 Part III {Station Engineer)

Design Inputs {i.e. Press, Temp, Corrosion, Wind, Seismic etc.)

'~~~~5~.-~: /885 5 is

A-1406: 14 TTACHMENT 1 CONTEND Evaluation:

uC e~ '

~c C'aa -(. QC'nl (3 WA

-er'y" . eM',Q~g t

b u 'ec e 4 pic Testing Requirements:

'A~ M vi u c 4 Safety Analysis: Attach documentatio er A-303 Mode Restrictions:

PREPARED BY: ~

DATE:

REVIEWED BY: DATE ~ /Z /Z F/

APPROVED BY: DATE:

PORC APPROVAL MEETlNG: 7/- r5o DATE:

SAFETY ANALYSIS TEMPORARY MODIFICATION 91- d8j5 H-P Tug' tv c ~nevsT PR'NJ tu REPAIR Rev.0 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION December 12, 1991 Prepared by: lZ rz Staf E ine r Date Reviewed by: !B//8/

Date Reactor Engineer Reviewed by: lA. r nager, Technical Egin er' D e Approved by: z. lz Chairman, PORC Date

SCOPE OF ANALYSIS The purpose of this analysis is to evaluate the safety consequences associated with performing temporary leak repairs on secondary non-safety related systems. Repairs will be performed by either applying a mechanical clamp or by welding a short length of pipe with a valve or plug/cap over the leak to isolate it. Pipe size will be limited to 2" nominal pipe diameter or smaller.

2.0 References 2~1 ANSI B31.1 Power Piping Code 1983 3.0 Structures S stems and Com onents Affected SSC 3 ' The temporary leak repair it will will not affect any SSC since be applied to non safety related systems only, it it will not change any system performance and will not be located such that it could impact safety related equipment.

4.0 Safet Functions of Affected SSCs 4.1 None 5.0 Effects on Safet 5.1 The proposed temporary modification will not have an affect on any safety fuctions since it will be a dead leg pipe, the materials shall meet the applicable line specification and any resulting additional loads will be within the ANSI B31.1 code allowables.

Since the added pipe is a 2" or less dead leg , no new flow paths or increased capacity will be introduced and any pipe breaks will be eveloped by the existing secondary pipe break analysis and isolated by the MSIV'S or Main Feedwater check valves 5.2 By preventing the temporary modification from being installed such that it could phisically impact safety related equipment, the seismic qualification of safety related equipment will not be affected.

Safety Analysis Page 1 of 3 Revision 0 Temp Mod 91-052 Date ~12 12 91

Unreviewed Safet uestion Conclusion 6~1 The addition of the piping with valve or mechanical clamp to non-safety related secondary systems will not increase the probability of occurances of an accident previously evaluated in the UFSAR because the added material will meet the piping specification and B31.1 stress allowables, the 3/4" dia line is below the minimum line size for high energy piping, and the lines capacity will not be increase or decreased.

6' The addition of the piping with valve or mechanical clamp to non-safety related secondary systems will not increase the probability of consequences of an accident previously evaluated in the UFSAR because the added material will meet the MS piping specification and B31.1 stress allowables, the 2" dia line is below the minimum line size for high energy piping, and the lines capacity will not be increase or decreased. Since the line capacity is not increased, there will not be an increase in the secondary heat removal.

6.3 The addition of the piping with valve or mechanical clamp to non-safety related secondary systems will not increase the probability of occurances of a malfunction of equipment important to safety previously evaluated in the UFSAR because the added material will meet the MS piping specific-ation and B31.1 stress allowables, the 3/4" dia line is below the minimum line size for high energy piping, and the lines capacity will not be increase or decreased. Consequen-tly, the original design function of the line will be maintained and therfore, no increase in equipment malfunctions are possible.

6' The addition of the piping with valve or mechanical clamp to non-safety related secondary systems not increase the of consequences of a malfunction of equipment important to safety previously evaluated in the UFSAR because the added material will meet the MS piping specification and B31.1 stress allowables, the 2" dia line is below the minimum line size for high energy piping, and the lines capacity will not be increase or decreased. Since the line capacity is not in-creased, there will not be an increase in the secondary heat removal.

6e5 The addition of the piping with valve or mechanical clamp to non-safety related secondary systems will not create a possibility for an accident of a different type than any evaluated previously in the UFSAR because the operation and the function of the line will not be changed.

Safety Analysis Page 2 of 3 Revision 0 Temp Mod 91-052 Date ~12 12 91

6.6 The addition of the piping with valve or mechanical clamp to non-safety related secondary systems will not create a possibility for a malfunction of equipment of a different type than any evaluated previously in the UFSAR because the function and capacity of the return line will not be changed and the existing pipe break analysis envelopes 2" lines 6.7 The addition of the piping with valve or mechanical clamp to non-safety related secondary systems will not reduce any margin of safety as defined in the bases of any technical specification because the temporay modification will not change the function any system and therefor will not affect the bases of any Technical Specification.

7.0 Conclusion The addition of the piping and valve or mechanical clamp does not constitute an unreviewed safety question based on the discussion presented in section 6.

Safety Analysis Page 3 of 3 Revision 0 Temp Mod 91-052 Date .i~212~9

A-1406:13 TEMPORARY MODIFICATION EVALUATION Part I Coor na or)

TM No.: ~~-el Date: </~ A>

Title:

FLLiCt. ~a VAiVC< t~gha. ~i~4 uPSVACh~ C f l.4- b4R II Part Type:

(Inltlator)

Electrical Fluid / Structural

==

Description:==

I e ~le" S5 m'q a i Vab c 1 6 to c b 4, ~ lOZ h gC Qcg g in -I a. CFaf t ih F th I -1o r in er ~i iver 0-1O ot m Ori'Ct eX.i +in Ef n rvn < 4t. cA 0 ( i C+ >~<'> 5%4c- 5 i~gow ~ C4cr~a pe% ~h 1 ~c>0i +~ s Part III (Station Engineer) ting, Design Inputs (i.e. Press, Temp, Corrosion, MindF Seismic etc.)

I.

• C~B' Yi 3-*

PrCSSu~- 35t70 Si: &<a t ~

S+t i'~ lT.~ g+eel +ahba SST 834 f RQGOr AM, li 0D ~ 0G~au~ t I. Va - ~ z (a/c. ssT 7" '3/g.

CihC iS h -5CtS&c Q 40 ASK

A-1406: 14 Evaluatio>: ~ b~cheA

~t.vi~- AZr ~

r >I ) - cv<r ~cl ww~7 A~5'c rc ck+5rc Testing Requirements

'(9r'>0~ Sr'~ ~~gC7 5r Safety Analysis: c do See ~ ffcc.hec0 Mode Restrictions:

PREPARED BY: DATE:

REVIEWED BY: DATE APPROVED BY: TP: I f PORC APPROVAL MEETING: DATE: / /> fZ-

EVALUATION FOR TEMPORARY MODIFICATION 92-01 Al The PCV-1022A FILTER AND ISOLATION VALVE INSTALLATION installation shown on the I/C shop (Steve Stinson) is to be attached sketches<

installed to

<~2,'3 4- 5a44 the prepared by the Cn non-code class portion of the waste gas system per drawing 33013-1273, sheet 2.

It is considered to be non-seismic, however position c(2) of USNRC Regulatory 'Guide 1.29 will be considered in the installation and will be discussed later in this evaluation.

The line specification for this section of tubing is 2505. This translates to a design pressure of 2500 psig at 650 degrees F.

The Waste Gas system (tanks and related piping) is designed for 150 psig per Gilbert Spec 5291. The Gas Decay Tanks have reliefs and rupture disks which limit pressure to:150 psig. Operating pressure is generally 110 psig or less and operating temperature is 50-140 degrees F. The primary components. to be used in this modification are stainless steel tubing, an isolation valve and a filter assembly. The tubing is to be stainless steel, 3/8" O.D.,

with a .065" wall thickness in accordance with the line specific-ation. The isolation valve is to be a Whitey SS-1VS4, rated for 3435 psig at, 450 degrees F. Both of these components meet or exceed all pressure requirements. The filter is a Balston type 45S6, maximum pressure 250 psig at 220 degrees F. This meets the system pressure requirements.

The new bracket, filter It willfasteners. and housing weighs approximately 6 pounds. be mounted to the wall using embedded unistrut and two 1/4" This fastening system is more than capable of restraining the weight of the new components as is required for temporary modifications. In addition, the only items which would be impacted if the restraining device were to fail during a seismic event are the copper air supply lines to valves 1036B, 1037B, 1038B, and 1039B. Since Instrument Air is not a seismic system, impact to these lines is not deemed to be a safety concern. All other items in the area are sufficiently protected from impact of the new components.

The modification involves portions of the non-code class lines as shown by the PEID. However the work is classified as safety significant per the Ginna Master Equipment Database and Licensing classification. The Ginna QA program is therefore applicable to the modification. However, QA material is not required. This is.

in accordance with paragraph 3.4.2.2 of procedure A-1406 and appropriate for the function that these components will serve.

As a good practice QA material should be used if possible.

Flow to (and from) the waste gas analyzer is controlled by three pressure regulators, a vacuum pump, bypass flow features and needle valves at the two analyzers. The addition of a filter and isolation valve will induce a new pressure drop into the system.

Cghey are located upstream of the pressure regulator. Therefore Ph< since there is a large (80-100 psig) pressure drop across the regulators any new drops at the low flow values experienced (6

cfh) will be adjusted for by the regulators. This will ensure that flow to the analyzers is within the system design require-ments.

SAFETY ANALYSIS TEMPORARY MODIFICATION 92-01 PCV-1022A FILTER AND ISOLATION VALVE INSTALLATION

'REVISION 0 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION JANUARY 3, 1991 Prepared by:

Sta En ineer Date Reviewed by:

Reactor Engineer Date Reviewed by:

M e , Te nical S ct'on ate Approved by: / /o/fz-Chairman, PORC Date

1.0 Sco e of Anal sis:

The purpose of this analysis is to evaluate the safety consequences associated with the addition of a filter and isolation valve upstream of PCV-1022A. These items are necessary to protect the control valve from partic-ulate matter that has been fouling it, causing frequent corrective maintenance.

1.2 PCV-1022A is the pressure control valve in the sample header of the Gas Decay Tanks to the MSA Gas Analyzer.

It is located in the tubing downstream of the ASME class break. The components of this modification are located in the tubing also, ensuring that there is no effect on the seismic, class 3 piping further upstream.

2 '

References:

2-1 USNRC Regulatory Guide 1.29, Seismic Design Classifica-tion.

2 ' RGGE Drawing 33013-1273, sheet 2, Waste Disposal Gas.

2.3 Gilbert Specification 5291.

2.4 Ginna Master Equipment Database.

~ ~

2.5 Swagelok Manual W-1287-4 2.6 Procedure A-1406, Control of Temporary Modifications.

2 ' Ginna UFSAR, section 3.9.2.1.3, 15.7.1, 11.3 2 ' Ginna Technical Specifications, sections 4.12.2, 5.5.2.

3 ' Structures S stems and Com onents Affected:

3.1 This modification, is to be installed in the waste gas system connected to the MSA Gas Analyzer. It will be break located downstream of the ASME Code Class and therefore has no effect on safety related systems, structures or components. The only SSC in the immediate vicinity to the modification are valvesvalves1036B, 1037B, which are 1038B, and 1039B. These are 3/4" NPS of higher section modulus than the tubing of the modification and are large enough components to be considered protected from impact of the modification items above (reference evaluation section of Temporary Permit 92-01). The new filter will be adequately secured in accordance with normal requirements for a temporary modification.

4.0 Safet Functions of Affected SSCs 4 ' The (4) valves in the vicinity remotely isolate the four gas decay tanks from the sample header and form the ASME class break.

5.0 Effects on Safet 5~1 The location of the new and modified components is in the non-code class tubing section of the sampling lines. This ensures that there is no direct effect on the lines upstream of the air operated isolation valves (1036B, 1037B, 1038B, 1039B) which are safety related and form the pressure boundary of the Gas Decay Tanks.

As previously discussed, the ASME Class 3 lines are large enough to afford inherent protection against a failure during a seismic event of the tubing and components above.

5.2 The new components will meet the line pressure require-ments and will no effect the ultimate flow delivered to the gas analyzer through the operation of the regulating valves. Therefore no system function will change due to this modification.

6.0 Unreviewed Safet uestion

Conclusion:

6~1 The addition of a filter and isolation valve to the waste gas system will not increase the probability of occurrence of an accident previously evaluated in the UFSAR because it is located downstream of the remote isolation valves of the Gas Decay Tanks. In addition it will meet all the requirements for pressure retaining capability.

6.2 The addition of these components will not increase the consequences of an accident previously evaluated in the UFSAR because it affects an non-code class section of the waste gas system and therefore is bounded by the current analysis for a gas decay tank rupture.

6.3 This modification will not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the UFSAR since be shown to have no effect on such items in the vicinity.

it has 6.4 This modification will not increase the consequences of a malfunction of equipment important to safety previously evaluated in the no effect UFSAR on such items since in the itvicinity.

has been shown to have

6.5 This modification will not create a possibility for an accident of a different type than any evaluated previo-usly in the UFSAR because the system function will not be affected and there is no effect on surrounding structures, systems or components.

6~6 This modification will not create a possibility for a malfunction of equipment of a different type than any evaluated in the UFSAR because it will enhance the operation and maintenance of the system and will have no effect on surrounding equipment.

6.7 This modification will not reduce any margin of safety as defined in the basis of any Technical Specification because it will not affect the function Specification.

and therefore the basis for any Technical of any system 7.0

Conclusion:

7.1 The implementation of this temporary modification does not constitute an unreviewed safety question based on the discussion presented in the previous section.

A-1406: 13 ATTACHMENT 1 TEMPO~@ MODIFICATION EVALUATION Part I (TM Coordinator)

OO-Q

,.: ~9z- Date:

Title:

Part II (Instigator)

Type: Electrical 2+ Fluid Structural

==

Description:==

Pii< C aw Q gtiC>~OCwA-'g ~on&( C.) Cj 0 g.SC. Rh~V~ C~+i A>~ i<~ ~ hC 7P H>> H A i.. ~

C.e l P 't~L ~ ~. g ~a,4c+

C.H3 (s~~ j . 'l ocF C& t

- ( 9 Cal'1 ee DXC G A~ 1 P "}~)M-l A.O4 S 'IA C9 ~~~ILa~c % O~c PV ~

Part III (Station Engineer)

Design Inputs (i.e. Press, Temp, Corrosion, Wind, Seismic etc.)

) ~ ol ) ag tk y l 1Q 9 5 4

/

Apl'Q-)

L era mohan c, cs+

0.,1 ~~ c, fcc)c eo -~c.5, e, o4 4c G.-i h, (4c>>t b(r C.al < .r

A-.14 06 14 TTACHMENT 1 CONT'D Evaluation:

e As Testing Requirements:

Safety Analysis: Attach documentation er A-303 Mode Restrictions:

PREPARED BY: DATE Z REVIEWED BY:4 DATE os E~rr APPROVED BY: DATE:

~ Sizar Ad~N9'ATE:

PORC APPROVAL MEETING:

P dtC RWCHH4ip e}A'Ci9Fo~A

SAFETY EVALUATXON TEMPORARY MODIFICATION 'l2- OC 2 Connection of Monitoring Equipment To Existing Test Points Rod Control System Rev. 0 Ginna Station Rochester Gas and Electric Corporation 89 East Ave Rochester, New York 14649 January 19, 1992 Prepared by:

Staff Engineer Date Reviewed by: l-r-Date Reactor En er 9

Reviewed by: '

Manager, Tech Engineerin Date Approved by: Q/- s'-p.~

Chairman, Plant Operati s Review Committee Date Po~WM d) P~~e

1' Scope of Analysis The purpose of this temporary modification is to connect monitoring instrumentation to existing test points in the rod control system. This modification is required to monitor for spurious signals in the rod control system causing a demand for rod out movement.

2 ' References 2.1 Plant Procedure A-1406, Control of Temporary Modifica-tions 2.2 Foxboro Drawing, CD-12 2.3 Updated Final Safety Analysis Report, Section 7.7 3.0 Structures, Systems, and Components Affected (SSC)

The system affected by this modificatiion is the auto rod control system.

4' Safety Function of Affected SSC's The function of the rod control system is to automatically respond to changes in reactor coolant system temperature and nuclear power (load pWrbations) to control reactivity and maintain or recover stable plant conditions with RCS Tavg within 1.5 degrees of program Tavg.

5.0 Effects on Safety The proposed modification will connect a 6 pen Gould recorder to 6 existing test points in the RSC rack (see reference 2.2). Normal monitoring the voltage drop across the resistor at the test point by the high impedance recorder will have no effect. on the loop signals generated in the auto rod control system. Failure of the test equipment would have no effect on 5 of the 6 signal loops. One of the six loops is a voltage loop where the potential failure would affect the variable gain input causing rods not to move at the required speed. Should rod control be in auto during this event, operator awareness of the test configuration and normal monitoring provides assurance that operator manual control of rods would maintain the plant stability.

6.0 Unreviewed Safety Question Conclusions The'proposed modification will not increase the probability of occurrence of an accident previously evaluated in the UFSAR because normal monitoring of the loop signals by this

test equipment will not affect the function of auto rod control.

The proposed modification will not increase the consequences of an accident previously evaluated in the UFSAR because there is no affect on the radiological barriers to a release of fission products.

The proposed modification will not increase the probability or consequences of a malfunction of equipment important to safety previously evaluated in the UFSAR. The purpose of this modification is to identify the source of an affect equipment malfunction. The test equipment will not normally the signals being monitored to the rod control system. Should a test equipment failure occur, operator awareness of the modified system configuration and normal operator response to rod control malfunctions will prevent consequences outside those evaluated in the UFSAR.

The proposed modification will not create the possibility of an accident or malfunction of equipment of a different type than any evaluated in the UFSAR. The proposed modification only affect the rod control system operation in auto.

Uncontrolled rod movement is evaluated in the. UFSAR in Chapter 15 which bounds any potential event resulting from this modification.

The proposed modification will not reduce any margin of safety as defined in the basis of any Technical Specification.

Rod control malfunctions are addressed in the UFSAR as discussed above. The proposed modification does not affect any margins of safety.

7.0 Conclusion Based on the above discussion the proposed modification does not present an unreviewed safety question.

A-1406: 13 ATTACHMENT 1 TEMPORARY MODIFICATION EVALUATION Part I (TM Coordinator)

TM No.: f2" 003 Date: 2 3 'F2

Title:

Bori ci'c( 7f'r~ er Rl /~

Part II (Instigator)

Type: Electrical Fluid Structural

==

Description:==

cpu~ Aa'i% eve r er A]M Part III (Station Engineer)

Design Inputs (i.e. Press', Temp, Corrosion, Wind, Seismic etc.)

Pun we b

> Zoo K t w+,We/ ~ >PhfY >~~M

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)I AU4 ~ I Ij'

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CONT'-1406 14 1

Evaluation:

~P/ 47 Aoc S 7 /5 eZ crW acP rw; le /dw H f'~ vier Asks re ace Ae Testing Requirements:

Safety Analysis: Attach documentatio er A-303 Mode Restrictions:

PREPARED BY: DATE:

REVIEWED BY: DATE APPROVED BY: DATE ~

PORC APPROVAL MEETING: DATE-

SAFETY EVALUATION TEMPORARY MODIFICATION Temporary Rigging to Remove The "A" Boric Acid Transfer Pump 92-003 February 2, 1992 Rev. 0 Ginna Station Rochester Gas and Electric Corporation 89 East Ave Rochester, New York 14649 Prepared by: 2 gZ'ate Staff Engineer Reviewed by: 2-React Engineer Date Reviewed by:

Manage c ical ngineering Date Approved by:

Chairman, Pla t Operations eview Committee at

1.0 Scope of Analysis The purpose of this analysis is to evaluate the safety consequences of attaching temporary rigging to the grating over the A Boric Acid transfer pump. Under the scope of A-1406, connecting temporary rigging to non-rigging identified points is considered a temporary modification.

2.0 References 2.1 Plant Procedure A-1406, Control of Temporary Modifica-tions 2 ' Interoffice Correspondence, dated March 30, 1987, Subject AFCAR 86-12:RD Item g2 Anchorage of 'Temporary Equipment at Ginna, From Leonard Sucheski To J. Widay 2.3 Ginna Technical Specifications section 3.2.2 and 3~3~1~1~

3.0 Structures, Systems, and Components Affected (SSC)

The boric Acid transfer system could be affected by this Temporary Modification.

Safety Function of Affected SSC's The boric Acid transfer system provides boric acid to the ECCS system for negative reactivity addition and shutdown margin.

5.0 Effects on Safety Since the temporary rigging is located 1 1/2 times its height from the opposite train of boric acid transfer components and any other safety related equipment, damage to the surrounding equipment under a seismic event is prevented.

In addition based on the'valuation of the rigging attachment provided in the Temp Mod evaluation, the rigging is within the load rating of the grating. The A train BA system is already out of service and covered by a Tech Spec LCO.

6.0 Unreviewed Safety Question Conclusions 6.1 The proposed modification will not increase the probability of occurrence of an accident previously evaluated in the UFSAR because the surrounding equipment will not be affected.

~02 02 92 Temp Mod'2-003 Page 1 Rev 0

- The proposed modification of an accident previously will not increase the consequences evaluated in the UFSAR because only the out of service train of the boric acid system will be affected 6.3 The proposed modification will not increase the probability or consequences of a malfunction of equipment important to safety previously evaluated in the UFSAR evaluated in the UFSAR because only the out of service train of the boric acid system will be affected 6.4 The proposed modification will not create the possibility of an accident or malfunction of equipment of a different type than any evaluated in the UFSAR because only the out of service train of the boric acid system will be affected 6.5 The proposed modification will not reduce any margin of safety as defined in the basis of any Technical Specification.

because only the out of service train of the boric acid system will be affected and LCO actions are already in place.

7.0 Conclusion Based on the above discussion the proposed modification does not present an unreviewed safety question.

02 02 92 Temp Mod 92-003 Page 2 Rev 0

A-1406: 13 ATTACHMEN TEMPORARY MODIFICATION EVALUATION part I (TM Coordinator)

TM No.: Q 'j-'C'ate: +

M Zi~N)i' 4'H 4 <.W ~rrgrllL g AJ PW&K~r CWi:inc. i.=. ~: i A& E t~~ (.VL.AMi Part II (Instigator)

Type: Electrical A Fluid Structural

==

Description:==

.~'l~'@~M( &NPO<W'PCC@r QQS P'o]A~~ /L) 744 in')4P(

v'OC III&(=

Part III (Station Engineer)

Design Inputs (i.e. Press, Temp, Corrosion, Hind, Seismic etc.)

c>iiui c-~ OILS As S AJ c)llJ 41 /4(M Dlc.rl(.',/r4 4: ~3 RD

A-1406- 14 TTACHMEN CONT'D Evaluation: I-(= l= t/A u /

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Safety Analysis: Attach documentation er A-303 P'/Cd'!0 Z-A(~ ~i I=uÃcu&>r Mode Restrictions:

PREPARED BY: DATE:

REVIEWED BY: DATE- M APPROVED BY DATE:

PORC APPROVAL MEETING: DATE:

r SAFETY EVALUATION TEMPORARY MODIFICATION Temporary Connection of Recording Equipment for Troubleshooting the Mag-A-Stat Voltage Regulator 92-004 02/06/92 REV. 0 Ginna Station Rochester Gas & Electric Corporation Prepared by

Staff Engineer Date Reviewed by:

Reactor gineer ate Reviewed by:

Manager, Technical Engineering Da e Approved by: ttMi ~

II Chairman, PORC Date

1.0 Scope of Analysis The purpose of this analysis is to evaluate the saf ety consequences of connecting temporary recording equipment to various points in the Mag-A-Stat Voltage Regulator. The recording equipment will gather data over an undetermined length of time, for the purpose of trouble-shooting the Regulator.

1.2 The following points will be monitored:

> Regulator Input Voltage

> Field Breaker Voltage

> Trinistat Input Voltage

> Trinistat Exciter Field Voltage

> Trinistat Exciter Field Current 2.0 References Plant Procedure A-1406, Control of Temporary Modifications Ginna Station UFSAR, Sections 10.2.2 & 10.7.6.8 2 ' Ginna Station Technical Specifications, Section 3.7 3.0 Structures, Systems, and Components Affected (SSC)

The Mag-A-Stat Voltage Regulator and Generator Field Excitation could be affected by this modification.

4.0 Safety Function of Affected SSC's 4.1 The Mag-A-Stat Voltage Regulator does not provide any function necessary for the safe shutdown of the plant.

4.2 The Ginna Station UFSAR, in section 10.7.6.8 addresses the Generator Exciter Cooling system in descriptive form only.

4.3 The Ginna Station Technical Specifications do not address Generator Excitation in section 3.7, Auxiliary Electrical Systems.

Temp Mod 92-004 Page 1 02/06/92 Rev 0

Cl 4 ' The Ginna Station UFSAR, in section 10.2.2 addresses Generator excitation in descriptive form only.

5.0 Effects on Safety 5' Since the Mag-A-Stat Voltage Regulator provides no safety function, there vill be no effect on plant safety by the temporary installation of recording equipment.

5.2 The recording equipment utilized vill have isolated, high impedance inputs so that no inadvertent failure of the Voltage Regulator, due to the recording equipment is anticipated.

6.0 Unreviewed Safety Question Conclusions 6.1 The proposed temporary modification will not increase the probability of occurrence of. an accident previously evaluated in the UFSAR because the system affected is not required-for the safe shutdown of the plant.

The proposed temporary modification will not increase the probability or consequences of a malfunction of equipment important to safety previously evaluated in the UFSAR because the system affected is not required for the safe shutdown of the plant.

6.3 The proposed temporary modification will not increase the consequences of an accident previously evaluated in the UFSAR because the system affected is not required for the safe shutdown of the plant.

6 ' The proposed temporary modification will not create the possibility of an accident or malfunction of equipment of a different type than any evaluated in the UFSAR because only the Mag-A-Stat Voltage Regulator and Generator Excitation could be affected.

6.5 The proposed temporary modification will not reduce any margin of safety as defined on the basis of any Technical Specification because only Generator Exciter Cooling is addressed in Technical Specifications on a description basis only.

Temp Mod 92-004 Page 2 02/06/92 Rev 0

7.0 conclusion 7.1 Based on the above discussion, the proposed temporary modification does not present an unreviewed safety question.

Temp Mod 92-004 Page 3 02/06/92 Rev 0

A 1406 13 TEMPORARY MODIFICATION EVALUATION Part I Coor na or

'72-oo5 ,. og (g z

Title:

Part II (In txator)

Type: Electrical Fluid + Structural D i tio: TRERf lS R LCM IlY 7NE VAJA UNF FRDrN SR Hayes VM Bu Z >E EPNDBllZH2. 77f6E QuLD ZE 7M PQQIZl,k P7EPHIEf. WAIJ7r9I.L H ck f!EM PA'i'A5 LrffMIT 6E -.

Ill/Jul.L 8 N/EPlF VP 7B 2" t/Y . Wkly 4 ELM MP LINE D ~~ LOC . MMVPODSQ.

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A 1406 ~ 13 ATTACHMEN ORARY MODIFICATION EVALUATION part: I (TM Coordinator)

TM No.: Date:

Title:

Illa'P~ nf o~ g Q r/V uiPM&V.r

~ k.M ( m C>PC~

t CAc~ c'~>7 mPP part II (Inxtxat:or)

Type: Electrical u Fluid St:ructural

==

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PREPARED BY: DATE:

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PORC APPROVAL MEETING: c-c DATE

SAFETY EVALUATION TEMPORARY MODIFICATION Temporary Connection of Recording Equipment for Troubleshooting Erratic Operation of Heat Trace Circuit ESP 92-006 02/28/92 REV. 0 a/aW/~~

P)yMiiuC Ginna Station Rochester Gas & Electric Corporation Prepared by:

Staf Engineer Date

'r Reviewed by: zlzzl~z.

Reactor Engineer Date Reviewed by:

r Techn'l Engineering D te Approved by: ~- 2/zH/g Z Chairman, PORC Date

-0

A-1406 13 TEMPORARY MODIFICATION EVALUATION par floor na or)

Date:

Title:

1/I Part II (In ta or)

Type: Electrical Fluid Structural

==

Description:==

/8h" a /5 e(

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SAFETY ANALYSIS l

TEMPORARY MODIFICATION 91-05 FLANGE HEATING STEAM RETURN ELBOW REPAIR Rev.0 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION December 10, 1991 Prepared by: l4 io +/

Staff Engi ee D te Reviewed by:

eactor Engineer Date Reviewed by:

Mana chnica E ineering Da Approved by: ri~ ~~]o +I l

Chairman, PORC Date

SCOPE OF ANALYSIS The HP turbine flange heating return line to the condenser has a 3/4" elbow with a small pin hole leak. The purpose of this analysis is to evaluate the safety consequences of welding a coupling or nipple to the elbow and inserting a og plug to stop the leak. Replacement of the elbow would gatv'C, require shutting the unit down since it is unisolatable.

2.0 References 2.1 GINNA P&ID 33013-123/2 2.2 Ginna UFSAR section 10.1.3.1, 15.1 3.0 Structures S stems and Com onents Affected SSC 3 ' The Main Steam system is the only system affected by this temporary modification.

4 ' Safet Functions of Affected SSCs The only Safety function the Main Steam system provides is to remove Reactor Decay Heat upon a Reactor trip via the MS safety relief valves.

4.2 As part of the MS system, the MSlV's provide MS header isolation in the event of High steam flow with an SI signal and low Tavg or High High steam flow with an SI signal.

5.0 Effects on Safet 5.1 The proposed temporary modification will not have an affect on the MS safety fuction since its down stream of the MSIV's.

]/RL~ ~

5.2 The addition of the nipple/coupling and plugl to the elbow will not reroute any flange heating steam flow nor will increase or decrease the lines capacity. The temporary modification will restore the integrity of the pressure boundary with material meeting or exceeding the MS line specification SP-5291 600-1. The flange heating return line is not required to be seismically installed. Consequently, the small amount of wieght added by the coupling and plug/vAiae.

will be well within the ANSI B31.1 code allowables.

Safety Analysis Page 1 of 3 Revision 0 Temp Mod 91-051 Date ~12 1D 91

6.0 Unreviewed Safet uestion Conclusion vni~ ~

6.1 The addition of the coupling/nipple and plug~ to the flange heating steam return line will not increase the probability of occurances of an accident previously evaluated in the UFSAR because the added material will meet the MS piping specification and B31.1 stress allowables, the 3/4" dia line is below the minimum line size for high energy piping, and the lines capacity will not be increase or decreased.

6.2 The addition of the coupling/nipple and plug to the flange heating steam return line will not increase the probability yCpfy"consequences of an accident previously evaluated in the UFSAR because the added material will meet the MS piping specification and B31.1 stress allowables, the 3/4" dia line is below the minimum line size for high energy piping, and the lines capacity will not be increase or decreased. Since the line capacity is not increased, there will not be an increase in the secondary heat removal.

6.3 The addition of the coupling/nipple and plug to the flange heating steam return line will not increase the probability of occurances of a malfunction of equipment important to safety previously evaluated in the UFSAR because the added material will meet the MS piping specification and B31.1 stress allowables, the 3/4" dia line is below the minimum line .size for high energy piping, and the lines capacity will not be increase or decreased. Consequently, the original design function of the line will be maintained and therfore, no incre'ase in equipment malfunctions are possible.

6.4 The addition of the coupling/nipple and plug to the flange heating steam return line will not increase the of con-sequences of a malfunction of equipment important to safety previously evaluated in the UFSAR because the added material will meet the MS piping specification and B31.1 stress allowables, the 3/4" dia line is below the minimum line size for high energy piping, 'and the lines capacity will not be increase or decreased. Since the line capacity is not in-creased, there will not be an increase in the secondary heat removal.

~ ~

695 The addition of the coupling/nipple and plug to the flange heating steam return line will not create a possibility for an accident of a different type than any evaluated previously in the UFSAR because the operation and the function of the line will not be changed.

Safety Analysis Page 2 of 3 Revision 0 Temp Mod 91-051 Date 12I210 91

- 6e 6 Thee addition of the coupling/nipp lee and pplug to the flange

'l heating steam return line will not create a possi 'b'lit nction of equipment of a different typee than i y for an any

't sl in the UpSAR because the function and capaci y ofo the return line will no b h d d th existing pipe break analysis envelopes 3 / 4" lines The addition of the coupling/nipp le and lu to the flange 6.7

'h b'l heating steam return line will not reduce any margin o safet as define d in e b a ses of any technical specification t

because the ur ine a nge heating is not part of the bases of any Technical Specification The addition of a nipple/coupling an d p lug to the turbine flan e heating return line does not constitute an unreviewe safety question b ase d on the discussion presented in section 6 ~

Safety Analysis Page 3 of 3 Revision 0 Temp Mod 91-051 Date ~110 91