HL-5320, 1996 Annual Operating Rept for Edwin I Hatch Npp,Units 1 & 2
| ML20135D018 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/31/1996 |
| From: | Sumner H GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HL-5320, NUDOCS 9703050012 | |
| Download: ML20135D018 (64) | |
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Georgia Power Company 40 invemess Center Parkw;y Birmingham. Alabarrc 35242 Telephone 205 870-6011 ;
Mailing Address:
Post Office Box 1295 Birmingham. Alabama 35201 g
GeorgiaPower ;
Nuclear operations Depar: ment the southern electnc system i
i February 28, 1997 Docket Nos. 50-321 HL-5320 50-366 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Edwin 1. Hatch Nuclear Plant Annual Operating Report for 1996 Gentlemen:
Enclosed is the 1996 Annual Operating Report for Edwin I. Hatch Nuclear Plant Unit 1, 1 Docket No. 50-321, and Unit 2, Docket No. 50-366. This report is submitted in accordance with the requirements of 10 CFR 50.59(b)(2) and Regulatory Guide 1.16.
Sincerely, 1
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- - h H. L. Sumner, Jr. 1 Vice President - Nuclear i Hatch Project l l
IFL/eb
Enclosure:
1996 Annual Operating Report for Plant Hatch Units 1 and 2 ;
cc: Georeia Power Company Mr. P. H. Wells, Nuclear Plant General Manager
- ')RMS l
U.S. Nuclear Reentatory Commission. Washineron. D.C.
Mr. K. Jabbour, Licensing Project Manager - Hatch U.S. Nuclear Reentatory Commission. Region 11 7 / l- ',
Mr. L. A. Reyes, Regional Administrator Mr. B. L. Holbrook, Senior Resident Inspector - Hatch /{ %
040119 gippsppppppy 9703050012 961231 PDR ADOCK 05000321 R PDR
i ENCLOSURE i
EDWIN I. IIATCII NUCLEAR PLANT- UNITS 1 AND 2 i
NRC Docket Nos. 50-321 and 50-366 Operating Licenses DPR-57 and NPF-5 ANNUAL OPERATING REPORT t 1996
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i TABLE OF CONTENTS f.8St ,
clossary..... ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... ii l Introduction.. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . .. . . . . . . 1
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10 CFR 50.59 Summaries for 1996.. . ..... . . .... .. , . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 I
Unit I/ Common As-Built Notices.. . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 !
Unit 2 As-Built Notices ...... .. .... .. .. . .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Unit 1/ Common Design Changes. ........ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 !
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Unit 2 Design Changes.. .
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Unit 1/ Common FSAR/ FHA Changes .. . . . . . . . . . . . 25 i
Unit 2 FSAR/ FHA Changes.. ... .. , . . . . . . . .. . . . . . 28 (
Bases Changes ... .. . . . . . ... . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . 30 .
Unit 1/ Common TRM Changes.. . . . . . . . . . . . , . . . . . . . . . . . . . . 32 l Unit 2 TRM Changes .... . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 Unit 1/ Common Minor Design Changes . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . 37 Unit 2 Minor Design Changes . .. .. . . . . . . . . . . . . . . . ... 39 r
Temporary Modifications. ... .. . . ..... . . . . . . . . . . . 41 !
Setpoint Design Changes.. .. .. . . . . . .. . . . . . .. . . . . . . . . . . . 45 :
Document Change Requests.. . .. . . . .. . .. . . . . . . . . . . . . . . . . .. . . . 46 :
Plant Deficiencies. . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 I Plant Procedures ... . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . 55 !
Data Tabulations and Unique Reporting Requirements. .... . . . . . . . . . . . . . . . 56 5 i
Occupational Personnel Radiation Exposure for 1996.. . 57 !
Regulatory Guide 1.16 Information End of Year Report - 1996. 58 l I
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GLOSSARY ACRONYMS AND ABBREVIATIONS i'
- ABN as-built notice AC alternatmg current I ADS automatic depressurization system ,
APLHGR average power linear heat generation rate APRM average power range monitor ARI alternate rod insertion ;
ASME American Society ofMechanical Engineers -
i ATWS anticipated transient without scram
- ATWS-RPT - anticipated transient without scram-recirculation pump trip [
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BOP balance of plant
- BWR boiling water reactor
! BWROG Boiling Water Reactor Owners Group !
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. CFR Code of Federal Regulations
) COLR Core Operating Limits Report l
} CRD control rod drive CS core spray. l i
CST condensate storage tank l
, DBA design basis accident l
. DC direct current j DCR - design change request j dP differential pressure *
- DoCR Document Change Request i
ECCS emergency core cooling system ECP- electrochemical potential
! EDG emergency diesel generator EFCV excess flow check valve EFPD effective full power days >
! EFPH effective full power hours i
! EGM electronic governor module ,
l EHC electrohydraulic control i i EOC-RPT end ofcycle-recirculation pump trip EPA Environmental Protection Agency 4 i i FHA Fire Hazards Analysis i FSAR final safety analysis report Page ii l
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GLOSSARY j l
ACRONYMS AND ABBREVIATIONS GE General Electric '
GL Generic Letter GPC Georgia Power Company l
t HCU hydraulic control unit l HNP Hatch Nuclear Plant i HPCI high pressure coolant injection [
HVAC heating, ventilation, and air-conditioning HWC hydrogen water chemistry I&C instrumentation and control !
IE inspection and enforcement -
IGSCC intergranular stress corrosion cracking i ILRT integrated leak rate test i
INWC inches water column '
IRM intermediate range monitor ;
ISI inservice inspection IST inservice testing l LCO limiting condition for operation LDS leak detection system l LLRT localleak rate test I LLS low-low set LOCA loss of coolant accident j!
LOSP loss of offsite power LPAP low power alarm point I LPCI low pressure coolant injection LPM loose-parts monitor
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i LPRM local power range monitor LPSP low power setpoint l M/A manual / auto MCC motor control center MCPR minimum critical power ratio MCR main control room MCRECS main control room environmental control system MDC minor design change MOV motor-operated valve MPL master parts list MSIV main steam isolation valve MSL main steam line MSLRM main steam line radiation monitor I
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GLOSSARY ACRONYMS AND ABBREVIATIONS NMA noble metals addition NPSH net positive suction head NRC- Nuclear Regulatory Commission NSSS nuclear steam supply system ODCM Offsite Dose Calculation Manual !
OPRM oscillation power range monitor PAM post accident monitoring l
PASS post accident sampling system l
PCIS . primary containment isolation system !
PCIV primary containment isolation valve l
P&ID piping and instrumentation diagram i PRB Plant Review Board !
PRNM power range neutron monitor !
PSW plant service water P/T pressure / temperature
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QA quality assurance RBM rod block monitor RCIC - reactor core isolation cooling RCPB reactor coolant pressure boundary RCS reactor coolant system REA request for engineering assistance RES request for engineering services RFP reactor feed pump RFPT actor feed pump turbine RG Regulatory Guide RHR residual heat removal RHRSW residual heat removal service water RMCS reactor manual control system RPS reactor protection system RPT recirculation pump trip RPV reactor pressure vessel RRS reactor recirculation system RSCS rod sequence control system RWCU or reactor water cleanup RWC RWCS reactor water cleanup system RWE rod withdrawal error RWM rod worth minimizer Page it
GLOSSARY ACRONYMS AND ABBREVIATIONS SAER Safety Audit and Engineering Review SAT station auxiliary transformer SBGT or standby gas treatment SGTS or SGT SCM stress corrosion monitor SED System Evaluation Document SJAE steamjet air ejector SNC Southern Nuclear Operating Company SRB Safety Review Board SR Surveillance Requirement SRM source range monitor SRV safety relief valve SSC system, structure, or component TBWD thrust bearing wear detector TCV turbine control valve THV torus hardened vent TIL Technical Information Letter TIP traversing incore probe TLD thermoluminescent dosimeter TRM Technical Requirements Manual TSV turbine stop valve Pagev
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCII NUCLEAR PLANT INTRODUCTION 1
The Edwin I Hatch Nuclear Plant is a two-unit facility located approximately 11 mile:; nonh of Baxley, Georgia, on U.S. Highway 1. The plant consists of two light water reactors. Unit I was licensed to operate at 2436 MWt through Cycle 16, and 2558 MWt thereafter. Unit 2 is licensed l
to operate at 2558 MWt for the remainder of the license. The maximum dependable capacity for 1996 on Unit I was 756 net MWe through May 1, afler which the maximum dependable capacity l was 805 net MWe. The maximum dependable capacity for 1996 on Unit 2 was 809 net MWe. I General Electric furnished the boiling water reactor, the nuclear steam supply system, the turbine, f and the generator for both units. The plant was designed by Southern Company Services, Inc., '
with assistance provided by Bechtel Power Corporation. The condenser cooling method employs induced-draft cooling towers and recirculating water systems with normal makeup supplies drawn from the Altamaha River.
The plant is a co-owned facility with ownership delegated as follows:
Georgia Power Company 50.1 %
Oglethorpe Electric Membership Cooperative 30.0 %
Municipal Electrical Authority of Georgia 17.7 %
City of Dalton, Georgia 2.2%
Licensing information for the units in as follows:
Unit 1 Unit 2 Docket Number 50-321 50-366 License Issued 08/06/74 (DPR-57) 06/13/78 (NPF-5)
Initial Criticality 09/12/74 07/04/78 Initial Synchronization 11/11/74 09/22/78 Commercial Operation 12/31/75 09/05/79 Georgia Power Company has sole responsibility for overall planning, design, construction, operation, maintenance, and disposal of the Edwin 1. Hatch Nuclear Plant.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT l
10 CFR 50.59 SUAISI AR1ES FOR 1996 l
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT UNIT 1/ COMMON AS-HUILT NOTICES L
94-0077. Rev. 0 .
This change modifies drawings and associated calculations to agree with wiring diagrams and the f plant as-built configuration for control rod cavity temperature elements 2T47-N052 and -N054.
This change does not modify the function of th: 2T47 Drywell Cooling System. t The 2T47 Drywell Cooling System is not a safety-related system and temperature elements 2T47-N052 and -N054 are not safety-related components. This change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined ;
, in the basis for any Technical Specification.
- 94-0213. Rev 0 i
This change removes instrument 2P33-N015 from drawings because it does not exist in the p t adds two pressure indicators and one drain valve, and revises two valves from "normally open' m ,
"normally closed." This change modifies the design as reflected in the FSAR. !
None of the affected components were safety related. The change had no adverse effect on any l safety system or safety components. The change does not reduce the margin of safety as defined l
in the basis for any Technical Specification.
- 95-0229. Rev. O This change, in conjunction with ABN 95-0230, corrects the P&ID and the elementary diagram of the Process Radiation Monitoring System in the Reactor Building exhaust plenum and the main l stack. These are documentation changes to document the existence of various equipment and i instruments. The fimetion and operation of the Process Radiation Monitoring System are not affected by this change.
The Process Radiation Monitoring System (IDll) is safety related. This change has no adverse effect on any safety-related systern or component. This change does not reduce the margin of safety as defined in the basis of any Technical Specification.
95-0230. Rev. O This change, in conjunction with ABN 95-0229, corrects the P&ID and the elementary diagram of i the Process Radiation Monitoring System in the Reactor Building exhaust plenum and the main stack. These are documentation changes to document the existence of various equipment or
. instruments. The function and operation of the Process Radiation Monitoring System are not affected by this change.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCil NUCLEAR PLANT l UNIT 1/ COMMON AS-BUILT NOTICES !
The Process Radiation Monitoring System (IDI1)is safety related. This change has no adverse '
efTect on any safety-related system or component. This change does not reduce the margin of safety as dermed in the basis of any Technical Specification.
i 96-0029. Rev. 0
- This change documents the piping and valve configuration of SRVs IR43-F3038B & -F3039B on
- diesel generator air start compressors IR43-C001B & -C010B to show the SRVs cannot be isolated from the compressors. This change does not modify the operation of this system.
' Valves 1R43-F3038B & F3039B are not safety related. This change has no adverse effect on any safety-related system or component. This change does not redae the margin of safety as defined i
] in the basis for any Technical Specification. ;
96-0070. Rev 0
- This change updates existing plant drawings to show the existing power supply for the heat tracing on the sample lines to the hydrogen analyzers.
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' Panel IR25-S124 is not safety related. This change has no adverse effect on any safety-related ;
system or component. This change does not reduce the margin of safety as defined in the basis for i 1 any Technical Specification.
I 96-0071. Rev 0 l i
This change updates existing plant drawings to show the existing power supply for the heat tracing j on the sample lines to the hydrogen analyzers.
Panel IR25-S124 is not safety related. This change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-0130. Rev. O j This change adds existing flanges (used to facilitate removal) on the inlet and outlet of a scram discharge volume SRV to the CRD System P&lD and isometric drawings. This change does not modify the function or operation of this system.
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The CRD System and the SRV are safety-relrted. This change has no adverse effect on the CRD System or any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCII NUCLEAR PLANT
.) l UNIT 1/ COMMON AS-BUILT NOTICES 1
l 96-0164. Rev. 0 )
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This change modifies drawing H-15360 and FSAR section 10.2.4 to eliminate the reference to 1
removable grating panels in the new fuel storage vaults. This change does not modify the function or operation of any system. I i I 1
The grating panel is not safety related. This change does not challenge any safety-related system or component and does not reduce the margin of safety as defined in the basis for any Technical
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCil NUCLEAR PLANT UNIT 2 AS-BUILT NOTICES 95-0181, Rev, O This change corrects SJAE P&ID 11-21056 (FSAR Figures 10.3-1, sheet 2, and 10.4-1, sheet 1) ;
to indicate strainer 2 Nil-D002A does not have a screen installed. This change does not modify i the function or operation of the SJAE.
Based on a vendor review of the orifice sizes on the SJAE steam nozzles, it was determined the ;
SJAE may be run without a screen installed in strainer 2N11-D002A, which is not safety related.
This change has no adverse effect on any safety-related system or component and does not reduce the margin of safety as defined in the basis for any Technical Specification.
95-0191. Rev. O This change replaces MSIV drain valves 2B21-F025B, -F026B, -F025D, & -F026D with equivalent valves to eliminate leaks. +
i Valves 2B21-F025B, -F026B, -F025D, & -F026D are safety related. This change has no adverse effect on the Main Steam System or any safety-related component. This change does not reduce l' the margin of safety as defined in the basis for any Technical Specification.
95-0207. Rev. O j
This change revises the P&lD for the Reactor Building C'osed Cooling Water System (2P42) to accurately reflect the location of valve 2P42-F107 which is a discharge isolation valve for sample panel 2P33-P102.
The sample panel and the isolation valve are not safety-related. This char.ge dces not reduce the margin of safety as defined in the basis of any Technical Specification.
95 0246 Rev. O This change replaces failed relay 2N36-K6A in panel 21121-P217 with an equivalent relay, based upon an equivalency determination. This change does not modify the ftmetion or operation of the '
Extraction Steam System.
The Extraction Steam System is not safety related. The overall function of this system remains unaffected by this modification. This change does not reduce the margin of safety as defined in the basis for any Technical Specification. I t'.g 4
1996 ANNUAL OPERATING REPORT EDWIN I. IIATCH NUCLEAR PLANT l
l UNIT 1/ COMMON DESIGN CIIANGE REQUESTS l i
- 83-205. Rev. O This change replaces the RWCU precoat pump IG31-C003 impeller and motor, and increases the i bruker size at the 600-V-AC non-essential MCC R24-S015 frame 2A to allow increased pump flow rate. This change does not modify the function of the RWCU precoat pump, but does increase the pump flow rates for better performance.
RWCU precoat pump IG31-C003 is not safety related. This change has no adverse effect on either the RWCU System or the 600-V MCC. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.84-034. Rev. O This change adds three corrosion product samplers in the water analysis room to improve trace metal analysis in the final feedwater, condensate demineralizer influent and condensate demineralizer efiluent streams. This change does not modify the function of the H 202 Analyzer System (1P33).
The H202Analyzer System is safety related. The installation of the corrosion product samplers provides a more efTective method of obtaining samples for trace metal analysis. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.89-062. Rev. O This change replaces the steam packing exhauster drain steam trap and strainer with an atmospheric drain tank to reduce condenser air inleakage and overflow to radwaste. This change does not modify the operation of the steam packing exhauster.
The drain tank, associated piping and all components are not safety related. This change has no adverse efTect on the main condenser. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.90-165. Rev. 0
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This change replaces the Mechanical liydraulic Control System for the RFPTs with an Electronic Hydraulic Control System to improve the reliability of the RFPT controls and the overall stability of the Feedwater System. This change does not modify the function of RFPT Control System.
The RFPT Control System is not safety related. The change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN I. liATCII NUCLEAR PLANT UNIT 1/ COMMON DESIGN CIIANGE REQUESTS91-009 Rev.1 This change modifies three Class IE (2R23-S003 & -S004, & 2S11-S007 ) and six non-Class lE (2R23-S005, -S006, -S007, -S008, -S009, & -S010 ) 600-V station service transformers by replacing TF-1 cooling fluid with silicon cooling fluid to meet EPA guidelines. This change does not modify the operation of these transformers or the electrical distribution system they serve.
Three transformers are safety related and six are not safety related. This change has no adverse effect on these transformers, the electrical distribution system they serve, or any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.91-069, Rev. O This modification decommissions and removes the RSCS which is no longer in use. (DCR 90-247 deleted the function of the RSCS and replaced it with the RWM. The RSCS was out of service, but was hard wired to the RMCS and abandoned in place.)
The RSCS is a safety-related system. This change has no adverse effect on the RMCS or any safety-related components. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.91-123 Rev. O This design modification replaces the Unit 1 LOCA and LOSP Eagle Timers utilized on the EDG )
System (IR43) with Agastat ETR relays. The primary function of the new safety-related Agastat I timing relay circuitry, augmented with auxiliary relays, is the same as the replaced Eagle Timer I circuitry. Upon receiving an initiation signal, the new set of safety-related relays actuates to reset ,
the load shed logic and sequence the PSW pumps onto the 4160-V-AC switchgear. l The EDG System (IR43) is safety-related. This change does not challenge any safety-relaNd system or component. This change does not reduce the margin of safety as defined in the basis for ;
any Technical Specification. !91-140, Rev. 2 This change replaces the 1/4-inch diameter sample line tubing with 1/2-inch diameter tubing and routes the tubing so it is properly sloped from the ofTgas hydrogen analyzer to the process tap.
This design change also adds test and vent valves to ease the calibration of hydrogen analyzer N62-N057A&B. This change does not modify the function of the system.
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1996 ANNUAL OPERATING REPORT EDWIN I. HATCil NUCLEAR PLANT UNIT 1/ COMMON DESIGN CllANGE REQUESTS OfTgas hydrogen analyzers N62-N009A&B and -N057A&B are not safety related. This change does not challenge any safety-related system or component. This change does not reduce the !
margin of safety as defined in the basis for any Technical Specification.92-090. Rev. 0 This change replaces the existing HPCI flow controller with a Yokogawa programmable i controller; removes the associated control amplifier, M/A station, square root converter, and flow indicator; and replaces five indicators with digital bargraph indicators. The new controller assumes the function of these components.
The HPCI System is safety related. The overall function of the HPCI System remains unaffected by this design modification. This change does not reduce the margin of safety as defined in the l basis for any Technical Specification. ;
! 93-011T. Rev. O This change adds a temporary ventilation feature in the Turbine Building to assist in the removal 3 of noble gases utilizing Control Building standby exhaust fan (lZ41-C008C). The temporary i ventilation system exhausts into the Reactor Building vent stack where the exhaust is monitored j for radioactive content prior to release to the environment. This char.ge does not modify the normal operation of the Control Building Ventilation System.
This temporary design change is not safety related and has no adverse efTect on any safety-related system. This change does not reduce the margin of safety as defmed in the basis for any Technical Specification.93-055 Rev. 0 This change modifies the following to eliminate A-46/IPEEE program outliers: panels 1HI1-P670, -P681, & -P663; MCCs 1R24-S002, -S003, -S029, & -S031; instrument support for l IP41-N520 & -N521; conduit lH11-P654-ES8-C073 & the box that feeds damper lZ41-F015; air handler units lZ41-B003 A, B, & C; air supply line for damper lZ41-F009B; air regulator for
] valves lZ41-F010B & -F028B; cable tray support IU-10ED; cable tray support ID-68; multiple i
cable tray supports at Control Building el. I12 ft that interact with the PSW piping system P41-TBWH pipe siipports; air handlers IT41-B006A&B; 1X43-P006A,B,&C (pneumatic electro relay cabinet). This change does not modify the function or operation of the associated systems.
I The modified equipment is safety-related. The change has no adverse effect on any safety-related j system or component. This change does not reduce the margin of safety as defined in the basis l for any Technical Specification. i
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCil NUCLEAR PLANT UNIT 1/ COMMON DESIGN CHANGE REQUESTS93-057. Rev. O l
1 l This change replaces the one-of-three turbine trip logic with two-of-three logic for low EHC fluid '
pressure, main turbine shaft low oil pressure, stator cooling inlet water low pressure, and stator i ,
cooling high outlet water temperature. This change makes the turbine trip function more reliable and does not modify the main function of the trip logic.
1 i The turbine tripping function is not safety related. This change has no adverse effect on any 4
safety-related system or component. This change does not reduce the margin of safety as defined i
in the basis for any Technical Specification.
j 94-024. Rev. 4 i
- This change adds the Unit I helper cooling tower to improve rz all tower performance and the
) maximum generation capability (unit performance) by approximately 10 to 11 MW. It also
- modifies a security camera location and yard fire protection to accommodate the new tower.
These changes do not modify the overall function of the Circulating Water System, plant Security
{ System, or the Fire Protection System.
l The helper cooling tower, the Circulating Water System, yard fire protection, and the plant !
Security System are not safety related. This change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.94-030. Rev. 0 This change modifies the physical geometry of the Division I sample return line of the Hydrogen / Oxygen Analyzer Sampling (IP33) System to eliminate condensation fouling of analyzer IP33-P001 A instruments. This change does not alter the function of the H2 02 Analyzer Sampling System.
l The H:0 Analyzer 2 Sampling System is safety-related. This change has no adverse effect on any
, safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1 1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT UNIT 1/ COMMON DESIGN CIIANGE REQUEST 3 W
94-037. Rev. O This change modifies Appendix R safe shutdown equipment to eliminate the need for TSI fire protection material and meet 10 CFR 50, Appendix R safe shutdown requirements. This change does not modify the operation of this equipment.
The Appendix R equipment is safety related. This change has no adverse effect on the Appendix R equipment and does not reduce the margin of safety as defined in the basis for any
- Technical Specification.94-04L Rev. O This change revises the following setpoints and calibration endpoints for numerous components 4
affected by operating parameters changed to accomplish operation at 105% of Rated Thermal
! Power (2558 MWt) as documented in the original plant operating license: SRVs, electronic
- backup SRV actuation trip units, ATWS-RPT and ARI trip units, LLS trip units, MSL high flow trip units, HPCI steam line high dP trip units, RCIC steam line high dP trip units, feedwater j control level and pressure recorder, RWM LPAP and LPSP alarm units, RPV level transmitters, and feedwater flow transmitter. This change does not afrect the function, operation, or logic of ,
any of the affected systems as addressed in the FSAR.
i Many of the components and systems afTected by this change are safety related or are relied upon
' to mitigate an accident. Evaluation has shown that these safety significant systems and equipment are capable of performing their required safety functions at uprated power conditions. This
, change does not reduce the margin of safety as defined in the basis for any Technical Specification.94-045, Rev. O This change to the RHRSW System allows the operator to temporarily defeat the pressure
- interlock with the RHR System via timers and a keylock switch during startup of the RHRSW 3 pump. This prevents the RHRSW System's heat exchanger, thermal relief valves, and other i
, components from experiencing pump shutoff head pressure during pomp startup. The timers are '
used to limit valve operation such that a potential leak while the interlock is defeated remains l within leakage release limits.
l' The RHRSW System is safety related. The change has no adverse effect on the RHRSW System,-
RHR System, or any other safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCil NUCLEAR PLANT .
UNIT 1/ COMMON DESIGN CIIANGE REQUESTS ,94-048. Rev. 0 l 4
This change lowers the low water level ATWS-RPT setpoint to minimize reactor vessel thermal stratification due to recirculation pump trips following reactor scrams, and reduces the possibility ,
of having to depressurize the RPV to atmospheric pressure if the temperature differential between :
the bottom head region and the steam dome approach the Technical Specifications P/T limits.
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The ATWS-RPT is supplied by ATTS, which is a safety-related system. The overall function of :
the ATWS-RPT trip remains unaffected by this design modification. This change does not reduce !
l the margin of safety as defined in the basis for any Technical Specification. ;
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94-053. Rev. 0 '
t This change replaces the limit switches for main turbine stop valves (IN30-F005, -F006, -F007, & !
-F008) with limit switches that meet 10 CFR 50, Appendix B criteria and are less susceptible to contact chatter due to vibrations and assigns new MPL numbers for the limit switches. This change does not modify the function of the stop valves or any system.
The limit switches are safety related. The implementation of this modification has no adverse i
effect on the function of the stop valves or any other safety-related system or component This j change does not reduce the margin of safety as defined in the basis for any Technical i Specification.95-001. Rev. O This change raises the alarm setpoint for N62-R608 associated with the Off-Gas System to eliminate nuisance high temperature alarms and to be in agreement with Operation and Instruction Manual SX-16966, which states the preferred process temperature for the off gas as it leaves the moisture-separator and is ahead of the reheater should be approximately 45'F. This change does not modify the function of this system.
I The Off Gas System (N62) is not safety related. This change has no adverse effect on safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
95 007. Rev 0 '
This change adds new seal in relays to the RHR pump start timing logic to eliminate the possibility of a 1-s delay to the starting sequence in case a voltage transient occurs when large loads are added to the diesel generators during a LOCA or LOSP. This change does not modify the intended function or operation of the RHR pump start logic.
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCll NUCLEAR PLANT UNIT 1/ COMMON DESIGN CIIANGE REQUESTS The RHR pump start logic equipment is safety related. This change has no adverse effect on the RHR pump start logic and does not reduce the margin of safety as defined in the basis for any Technical Specification.95-017. Rev.1 This change replaces the generator assembly for EDG 1 A with a Class lE compatible replacement i generator to eliminate stator winding end turn movement and possible coil degradation. This '
change does not modify the function or operation of the EDG System (R43-S001 A).
The EDG System is safety related. This change has no adverse effect on the Diesel Generator System. This change does not reduce the margin of safety as defined in the basis for any Technical l Specification. '95-022, Rev. O The existing fuel grapple head equipped with an obsolete portable underwater television camera and monitor system was replaced with a new permanently mast-mounted and remote control camera (NF500TV system). The new NF500TV system was permanently mounted on the operator's cab and equipped with two monitors, a video distribution amplifier, a camera control console, and a camera remote control. The new NF500TV system improves the ability to handle fuel assemblies and perform verification activities associated with core ofiload and reload.
The new TV camera and lens system installed on the new grapple head assembly enables the ;
operators to read the serial numberi. on the bails of the fuel bundles, thus providing positive l identification of fuel bundles. The new grapple head makes it easier to perform refueling task and !
reactor core surveillance. '
The Refueling System (IF15) is a safety-related system; however, the mast is classified as j nonsafety-related equipment. This change has no adverse effect on the system or any safety-
{
related components. This change does not reduce the margin of safety as defined in the Bases for i any Technical Specification. 1 l
95-026, Rev. O This change relocates 13 Nuclear Boiler System instrument line EFCVs IB21-F041, -F043A&B,
-F045A&B, -F047A&B, -F049A&B, -F051 A&B, and -F053 A&B to provide room to add a test l connection upstream, and an isolation valve and test connection downstream of each EFCV to allow testing of the EFCVs during an outage with no pressure in the vessel. Also, this change adds platforms to allow plant personnel access to the isolation and test valves. This change does not modiFj the function or operation of the Nuclear Boiler System.
The EFCVs are safety related; however, the platforms are not safety related, but are designed to ,
Seismia !!!! criteria. This change has no adverse effect on the Nuclear Boiler System or any other I 1
Page 13 l
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT UNIT 1/ COMMON DESIGN CIIANGE REQUESTS safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.95-034. Rev. O This change replaces the existing Main Stack Obstruction Strobe Lighting System with a more reliable and maintainable system that meets FAA requirements. This change does not modify the function or operation of the system.
The lighting system is not safety related. This change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defmed in the basis for any Technical Specification.95-035. Rev. O This change adds a new parallel cable (R23-S004-ES4-M09A) which parallels existing cable R23-S004-ES4-M09) from Turbine Building switchgear 1R23-S004 to Diesel Building MCC 1R24-S027 to improve voltage level. This modification will not change the function or operation cf the equipment or systems supplied by these power sources, or any control logic associated with the affected equipment or systems.
The equipment is safety related. This change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any ;
Technical Specification. l 95-044T, Rev. O This change adds a temporary Chilled Water System water supply to provide temporary cooling of the PSW supply to the drywell coolers to reduce the drywell temperature. This change does not modify the function or operation of the Drywell Cooling or PSW Systems. )
The temporary Chilled Water and Drywell Cooling Systems are not safety related. The PSW system is safety-related. This change has no adverse efTect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.95-047, Rev.1 l
This change modifies the IB swing diesel generator from the original blower-turbo arrangement to the newer and improved turbo-blower series arrangement used on Unit 2 to reduce exhaust smoke, lower exhaust temperatures and reduce piston and liner temperatures. This results in longer engine life through decreased wear. This change does not modify the function or operation Page 14
1996 ANNUAL OPERATING REPORT EDWIN 1. HATCH NUCLEAR PLANT UNIT 1/ COMMON DESIGN CIIANGE REQUESTS of the diesel generator. The modification to the diesel also requires a modification to the air intake ,
piping to be similar to Unit 2 piping.
Diesel generator 1B and the intake piping are safety related. The modification has no adverse efTect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.95-048. Rev. 0 ,
This change modifies the voltage transfer logic for diesel generators lA and IC and allows switching from the manual to the automatic mode of operation for the voltage regulator to assure the diesels remain in the automatic mode during an LOSP event.
The diesel generators are safety related equipment. This design change does not adversely affect the design function or the performance of the standby ac power supply or its support components. !
This change does not reduce the margin of safety as defined in the basis for any Technical Specification.95-058, Rev. O This change c'!ows removal of motors installed on valves lEll-F021 A&B,1 Ell-F028A&B, i 1 Ell-Fil9A&B, and IE21-F004A&B to inspect for cracks in the motor shafts and allows installation of slower speed (1700 vs 3400 rpm) motors should a cracked motor shaft be discovered. This change modifies the operation of the MOVs by increasing the design stroke time from 10 to 20 seconds.
The motors installed on IEll-F021 A&B, IEll-F028A/B, IEll-Fil9A&B, and 1E21-F004A&B are safety related. This design change has no adverse effect on the MOVs. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.95-062, Rev. O This change adds isolation transformers to the alternate AC control power supplies for the remote !
shutdown panel to efTectively create an ungrounded alternate supply and precludes the possibility l of transferring control power to an alternate source with an undetected ground which would result j in a loss of control power. ;
The remote shutdown panel is passively safety related. This change will enhance its reliability and will not adversely affect its ability to perform its intended safety function. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN 1. HATCII NUCLEAR PLANT UNIT 1/ COMMON DESIGN CHANGE REQUESTS95-063. Rev. O This change proposes the use of GE-12 fuel assemblies for either unit's reactor core to deliver more energy, maintain or improve thermal power margins, and maximize overall economic ;
performance of the reactor. This change does not modify the function of the reactor core.
The GE-12 fuel is safety related. This change has no adverse effect on the reactor core. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.95-064. Rev. O This change replaces the existing DC power supply for the RCIC speed control signal loop with inverter power. The power source for the RCIC EGM, which was directly ofrDC power, is being moved to RCIC inverter power then convened back to DC via a new AC to DC isolating power supply. This change is being made to prevent RCIC coriponent degradation due to DC grounds.
This change does not modify the function of the RCIC System.
The RCIC System is not safety related but is treated as safety related. The overall function of the RCIC System remains unaffected by this design modification. This change has no adverse effect i on any safety-related system or component. This change does not adversely reduce the margin of safety as defined in the basis for any Technical Specification.
96-011T Rev. O This change adds a temporary Chilled Water System to provide temporary cooling of the PSW l supply to the drywell coolers to reduce the drywell temperature. This change does not modify the function or operation of the Drywell Cooling or PSW Systems.
1 The temporary Chilled Water and Drywell Cooling Systems are not safety related. The PSW !
System is safety-related. This change has no adverse efTect on any safety-related system or l component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.96-028, Rev. O This change modifies the annunciator wiring for the 600-V system to match the elementary drawings. This change removes R24-S001 from the "600V Bus Ic Breaker Tripped" annunciator on Panel lHil-P652 and adds it to the "600-V Sta Svc Fdr Brkr Trip" annunciator on panel 1Hil-P650. This change removes R24-S004 from the "600-V Bus ID Breaker Tripped" annunciator on panel lH11-P652 and adds it to the "600-V Sta Svc Fdr Brkr Trip" annunciator on panel 1H11-P650. These changes do not affect the operation of the 600-V system.
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1996 ANNUAL OPERATING REPORT ' EDWIN I. IIATCII NUCLEAR PLANT UNIT 1/ COMMON DESIGN CHANGE REQUESTS !
l The 600 V system is safety related; however, the annunciation of breaker trips is not safety ;
related. This annunciation change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification. :
t F
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i 1996 ANNUAL OPERATING REPORT EDWIN I. HATCH NUCLEAR PLANT UNIT 2 DESIGN CHANGE REQUESTS87-126. Rev. 0 This change adds a water treatment system to the Reactor /Radwaste Building Chilled Water '
System. This change does not change the operation of the system, but provides a means for !
controlling the pH, conductivity, and corrosivity of the system. i j The Reactor /Radwaste Building Chilled Water System is not a safety-related system. It is located !
outside the power block and handles nonradioactive water. This change does not adversely effect l any safety-related system or component. The change does not reduce the margin of safety as defined in the basis for any Technical Specification.
k 88-038. Rev. 0 This change modifies the HPCI pump turbine to eliminate further loss of chrome plating from the turbine shaft by removing the second inner carbon ring of the turbine casing gland seal. This !
I change does not modify the operation of the HPCI turbine. I The HPCI pump turbine is safety related. This change does not adversely effect any safety-related a
system or component. The change does not reduce the margin of safety as defined in the basis for any Technical Spe;ification.
3 88-115 Rev. O This change replaces the existing Reactor Building and Radwaste Building Chilled Water System controls with microprocessor controls and new temperature sensors in the chilled water supply and return lines to increase equipment reliability and extend equipment life. This change does not l modify major functions of the system but does require operational changes as described in the l FSAR.
. The Chilled Water System (2P65)is not safety related. This change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
i 89-282, Rev. 0 This change adds the torus hardened vent bypass line around the SGTS (2T46) and modifies the i SGTS and the Primary Containment Purge System to allow a direct flow path from the i
suppression pool to the plant stack, bypassing the SGTS filters. Suflicient isolation is provided to assure this change does not compromise existing safety functions provided for DBAs.
i The Primary Containment Purge and Inerting System, the Non-Interruptible Instrument Air
! portion of the Instrument Air System, the SGTS, and the Class 1E Electrical Distribution System are all safety related. This change does not adversely efTect any safety-related system or Page 18
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCH NUCLEAR PLANT UNIT 2 DESIGN CHANGE REQUESTS component. The change does not reduce the margin of safety as defined in the basis for any Technical Specification.
5 91-012. Rev. O !
This change modifies the Class IE 600-V station service transformers 1C (IR23-S003),
i ICD (ISil-S007), and ID (IR23-S004), for compliance with EPA requirements. This change l (replacing TF-1 cooling fluid with silicon cooling fluid) does not modify the operation of these
, transformers or the electrical distribution system they serve.
1 i These transformers (1R23-S003, ISil-S007 and 1R23-S004) are safety related. This change has l
. no adverse effect on theses transformers, the electrical distribution system they serve, or any !
safety-related system or component. This change dces not reduce the margin of safety as defined in the basis for any Technical Specification.91-070 Rev. O i DCR 90-247 was issued to delete the function of the RSCS and replace it with the RWM to perform the same function. The RSCS system was out of service but hard wired to the Unit 2 RMCS and abandoned in place. This modification is to decommission and remove totally the RSCS system which is no longer in use.
5 The RSCS is a safety-related system. This change has no adverse effect on the system or any safety-related components. This change does not reduce the margin of safety as defined in the Bases for any Technical Specification.92-071 Rev. O This change replaces drain line hangers 2N22-HD-H48, H49, & H50 with rod-type hangers to 3
eliminate the calibration problems experienced from the relaxed springs in the hangers. This !
- change does not modify the operation of the 7th stage heaters. j 4
The hangers are not safety related. This change has no adverse elTect on any safety-related system or equipment. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
92-162T, Rev. O This change adds a temporary ventilation feature in the Turbine Building to assist in the removal of warm air and noble gases. The temporary ventilation system exhausts into the Reactor Building wnt stack where the exhaust is monitored for radioactive content prior to release to the environment. This change does not modify the operation of the Turbine Building Ventilation System.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT UNIT 2 DESIGN CIIANGE REQUESTS This temporary design change is not safety related and has no adverse effect on any safety-related system. This change does not reduce the margin of safety as defined in the basis for any Technical Specification. !
l 93-038 Rev. 0 l
l This change replaces the existing hiSIV pilot solenoid valves with a new configuration since the existing ones are no longer available. The new valves are similar AVCO solenoid cluster supplied by General Electric. The existing resistor is upgraded to ensure the minimum voltage i requirements are met for the solenoids to opera:e.
The new assemblies are safety related and environmentally qualified. This change does not alter ,
the function of the hiSIVs or their control, and does not adversely affect the ability of the hiSIVs 1 to perform their safety function. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.93-049 Rev. O This change deletes isolation function of the PSW high flow signals from dP switches P41-N522 -
525 and reroutes the signal to allow annunciation on window P009 of main control panel H11-P650. Changing from automatic to manual isolation for nonsafety portions of the PSW System on receipt of a high flow signal and the accompanying addition of the high flow l annunciation will not adversely afTect the function or operation of the PSW System. 1 The PSW System is a safety-related system. This change has no adverse effect on safety systems ;
i or components. The change does not reduce the margin of safety as defined in the basis for any Technical Specification.
94 001, Rev. O This change replaces the 2N22-D345 strainer and associated drain piping from the steam packing exhauster (2N33-B001) to the main condenser (2N61-B001 A&B) with an atmospheric diain tank to mitigate the air in-leakage to the condenser This change does not modify the function of the Auxiliary Drain and Vent System (2N22), hiain Steam System (2N33), and Con %er System (2N61).
The Auxiliary Drain and Vent System is not safety-related. This change has no adverse efTect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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- 1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCil NUCLEAR PLANT )
i UNIT 2 DESIGN CIIANGE REQUESTS l
l
)94-003. Rev. 0 1
, This design change removes the testable features of CS check valves 2E21-F006A&B since .
~
I alternate methods are used to test the valves. The valves now function as simple check valves and retain their pressure isolation function between the reactor and core spray piping.
\
CS check valves 2E21-F006A&B are considered to be safety-related valves. This design change :
does not adversely affect the safety function of the CS System. This change does not reduce the ,
y margin of safety as defined in the basis for any Technical Specification. l
.94-017. Rev. O
! i This change modifies items to comply with the requirements of the Seismic Margin Assessment
)
{ ;
j Methodology (EPRI NP-6041) or the Seismic Qualification Utility Group Generic l Implementation Procedure for resolution of Unresolved Safety Issue A-46. l 1
These modifications apply to both safety related and nonsafety-related items. This change does j not reduce the margin of safety as defined in any Technical Specification.
l 1
94-021. Rev. 0
Main Steam, Condensate and Feedwater, Extraction Steam, Reheat, and PSW Systems to allow the valves to fully open or close against specified differential pressures. This change does not l modify the function or operation of these systems.
The valves in the HPCI, RCIC and PSW Systems are safety-related. This change has no adverse !
. efTect on any safety-related system or component. This change does not reduce the margin of 3
safety as defined in the basis for any Technicd Specification.
- 94-046. Rev. 0 This change modifies the RHRSW System to allow the operator to temporarily defeat the pressure interlock with the RHR System via a keylock switch during startup of the RHRSW pump and prevent the RHRSW System's heat exchanger, thermal relief valves, and other components from experiencing pump shutoff bead pressure during pump startup. Once the RHRSW pump has been started, the keylock switch is returned to its normal position, restoring the pressure interlock. The pressure interlock serves to prevent leakage of radioactive material from the RHR System to the ,
river.
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCII NUCLEAR PLANT UNIT 2 DESIGN CIIANGE REQUESTS The RHRSW System is safety related. The change has no adverse effect on the RHRSW System, the RHR System, or any other safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.95-031 Rev. O This change adds a seal weld around the head flange joint of RWCU heat exchanger 2G31-B001C to contr.in leakage. This change does not modify the function of the RWCU system.
The seal weld is not safety related. The installation of a seal weld and use of an approved leak repair sealant will have no adverse effect on the overall original design, structure, system, or component, nor will it affect the RWCU System's modes of operation. This change does not
, reduce the margin of safety as defined in the basis for any Technical Specification.95-042 Rev. O This change proposes the loading of GE-13 fuel (4 assemblies) in the reactor core and also modifies the GE-13 fuel bundle debris filter to prevent larger debris particles from getting into the fuel assembly. These changes do not modify the function of the reactor core.
The GE-13 design fuel and the lower tie-plate debris filter are safety related. This change has no adverse efTect on the reactor core. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.95-049. Rev. O This change modifies the voltage transfer logic for diesel generators 2A, 2C, and 1B and allows switching from the manual to the automatic mode of operation fo: the voltage regulator to assure the diesels remain in the automatic mode during an LOSP event.
The diesel generators are safety-related equipment. This design change does not adversely afrect the design function or the performance of the standby ac power supply or its support components.
This change does not reduce the margin of safety as defined in the basis for any Technical .
Specification. I I
95-059, Rev. O This change eliminates the need for (and abandons) defective flow controllers 2T49-FIC-R602A&B by allowing 2T49-FIC-R601 A&B to provide low flow alarm and minimum flow permissive signals, and permanently removes power to the control circuits for valves 2T49-F008A&B with the valves in the closed position.
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCII NUCLEAR PLANT UNIT 2 DESIGN CIIANGE REQUESTS The combustible gas control system (CGCS) is a safety-related system. This design change provides for the hydrogen concentrations inside containment to be maintained below limits set forth in FSAR. This change does not reduce the margin of safety as dermed in the basis for any Technical Specification.95-061. Rev. O This change adds isolation transformers to the alternate ac control power supplies for the Remote ,
Shutdown Panel. This will effectively create an ungrounded alternate supply and will preclude the j possibility of transferring control power to an alternate source with an undetected ground which l would result in a loss of comrol power.
The Remote Shutdown Panel is passively safety related. This change will enhance its reliability !
and will not adversely affect its ability to perform its intended safety function. This change. does not reduce the margin of safety as defined in the basis for any Technical Specification. 1 1
95-070T. Rev. 0 l
This change adds temporary decontamination equipment on the Unit 2 Refueling Floor to perform l decontamination which will reduce personnel radiation exposures in accordance with the concept I of ALARA. This change does not modify the operation of the system. l Portions of the Fuel Pool Cooling System at tie-ins to the RHR System and the fuel pool itself are safety related. This change has no adverse effect on this system. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
l Page 23
. -. - - -. - - . . . .. ---- _-_ .- -.- . ~ . - -
1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCII NUCLEAR PLANT i i
UNIT 1/ COMMON FSAR/FIIA CilANGES i
FCF 11D-003 f
This change to FHA sections 4.4 and 6.0 addresses the combustible and ignition source control features to more accurately describe the current fire protection program; modifies terminology requiring a foreman to issue " hot" work permits rather than " hot" work procedures; and corrects ;
an erroneously referenced procedure number. These changes in practice descriptions have no ,
impact on any precursor to a transient or accident and do not affect the operation of any system or j component involved in the transient or accident. These changes, which provide a more accurate description of the fire protection program and responsibilities, reflect established and approved plant practices.
The margin of safety as defined in any Technical Specification is not reduced by this change to the l FIIA. '
FCF 14B-011 ,
This revision to the FSARs reflects a change in the post accident sampling program at Plant Ilatch ;
l from the use ofin-line analyzers to a grab sample program for performing boron, chloride, and pH i analysis on reactor coolant. This change is in compliance with NUREG-0737, Item II.B.3, and l Regulatory Guide 1.97 which require licensees to have the capability to obtain samples of reactor l coolant and containment atmosphere under accident conditions and to perform cenain analyses on l the samples. This change does not introduce a change in the design of the PASS or change the
- radiological characteristics of the fuel or the RCS. Existing plant equipment will be used for l obtaining the grab sample, with the exception of approximately 10 fl of 3/8-inch tubing and 4 j valves. No change in the installed plant equipment is involved in this change. t l !
The PASS is a nonsafety-related system. This change does not reduce the margin of safety as defined in any Technical Specification.
FCF 14B-023 :
This FSAR change revises Unit 1 Tables 8.4-1,8.4-9,8.4-10, and 8.4-11; adds Tables 8.4-13, 8.4 14, and 8.4-15; and revises subsections 8.4.3 and 8.4-4; Unit 2 Tables 8.3-6, 8.3-11 through 8.3-16; adds Tables 8.3-18, 8.3-19, and 8.3-20; and reviscs paragraphs 8.3.1.1.3 and 8.3.1.2.1 to reflect the revised steady-state loading on the EDGs for a LOCA/LOSP concurrent with a single l failure of an EDG or EDG battery and their buses. (Reference Unit 1/ Common DCR 91-123 for l further discussion of this change.)
FCF 14C-004
- This activity represents a change to the FSARs to provide for the use of earthquake experience data as an alternate method for verifying the seismic adequacy of new and replacement equipment to withstand a DBE and continue to perform its intended function. This change is part of the Page 24
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCli NUCLEAR PLANT '
UNIT 1/ COMMON FSAR/FIIA CIIANGES resolution of Unresolved Safety Issue A-46 as required by Generic Letter 87-02. The method of verifying seismic adequacy was developed by the Seismic Qualification Utility Group and is contained in the NRC-approved Generic Implementation Procedure.
This FSAR change does not modify any plant equipment or change the way the equipment is .
operated, but does provide for an alternate method for verifying the seismic adequacy of the !
equipment. This change does not reduce the margin of safety as defined in the Technical Specifications since regulatory requirements continue to be satisfied and the radiological consequences of a postulated DBA remain within regulatory limits.
i FCF 14C-022 I This revision to the FSAR changes Table 5.2-5 to reflect the correct instmment range of drywell '
pressure as -5 to +5 psig and adds the Narrow Range Torus Level which was inadvertently omitted from the Table. This change involves indicated range changes only and does not alter any .
equipment or system, and does not change the operation of any equipment or system.
No permissible operating conditions, setpoints, sequences of events, or time periods are affected by this change to the FSAR. This revision does not reduce the margin of safety as dermed in any Technical Specification. >
FCF 14D-001 This administrative change expands the information contained in Table 7.3-1 to be consistent with TRM Table T7.0-1, Primary Containment Isolation Devices - Testable Penetrations. Information, such as pipe schedule and sleeve size, is being moved from Table 5.2-2 to Table 7.3-1, and Table ;
5.5-2 is being deleted. Neither the actual physical condition or operation of the PCIVs, nor the l isolation capability of the containment penetrations is altered by this administrative change.
The margin of safety as defined in any Technical Specification is not reduced by this purely administrative change.
FCF 14D-0013 This administrative change to the FSARs is the result of a review of the MCRFC System descriptions to ensure consistency among design documents. This effort is the result of the Technical Specifications Improvement Program. These changes document system configuration as noted in calculations and the Technical Specifications and clarify functional and operational requirements of various MCREC System equipment. These changes reflect the as-built l
configuration of the plant. The operation of the MCREC System is not affected by this change. 1 No physical modifications are involved. l l
Page 25 l
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1996 ANNUAL OPERATING REPORT EDWIN I. HATCH NUCLEAR PLANT UNIT 1/ COMMON FSAR/FIIA CilANGES The margin of safety as defined in any Technical Specification is not reduced since the change achieves consistency with the Technical Specifications.
FCF 14D-0018 This administrative change to the FSARs is the result of The Southern Company's newly implemented SHIPS and STARS programs which are the byproduct of the standardization process within the Southern electric system. The FSARs will be made consistent with the Hatch Corporate and Plant organizational charts. This change does not alter any plant equipment or structure, and does not affect the operation of any plant equipment or system. No new failure modes are introduced by this purely administrative / editorial change.
This administrative / editorial change does not afTect any Technical Specifications safety analyses, limiting safety system settings, or limiting conditions for operation. Thus, the margin of safety as dermed in any Technical Specification is not reduced.
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l 1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT ,
1 i l
UNIT 2 FSAR/FIIA CIIANGES I l
FCF 14B-001 This purely administrative change to FSAR section 17.2 addresses changes in organizational titles and the location where activities are performed. No changes to plant equipment or operation of any system or component are being made. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
FCF 14H-024 This revision to FSAR Table 7.6-9 changes the Narrow Range Torus Level from 133 to 163
, INWC to reflect the correct calibrated instrument range. This change does not alter any equipment or system and does not change the operation of any equipment or system.
No permissible operating conditions, setpoints, or time periods are affected by this change to the FSAR. This revision does not reduce the margin of safety as defined in any Technical i Specification.
l FCF 14C-008 i
This change revises FSAR paragraph 9.4.2.2.3 to reflect the permanent design temperature limit i
, for the HPCI and RCIC pump rooms of 148 F. This change is consistent with the design of these i
- systems and their supporting instrumentation, and does not affect the accident analysis. No new j 4 design element is being introduced. The function and operation of the HPCI and RCIC Systems j are not afTected by this change. '
, The margin of safety as defined in any Technical Specificata is not reduced, since the change is consistent with the original design basis.
FCF 14D-009 This administrative change to section 13.1 indicates that the Nuclear Security Manager reports to the Manager of Plant Administration and not to the Plant Support Assistant General Manager.
This change does not affect the operation of any plant system and does not alter any system, component, or structure.
. This administrative change does not represent a reduction in commitments to the NRC. The margin of safety as defined in any Technical Specification is not reduced by this purely
- administrative change.
FCF 14D-0012 This administrative change to sections 13.4,13.48,13.6, and 17.2 is the result of Technical Specifications Amendments 195 (Unit 1) and 135 (Unit 2) which approved the conversion to the Page 27
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1976 ANNUAL OPERATING REPORT EDWIN I. HATCH NUCLEAR PLANT !,
j UNIT 2 FSAR/ FHA CHANGES j i ;
i j Improved Technical Specifications. This administrative change relocated certain administrative !
control requirements from the Technical Specifications to other licensing documents such as the !
FSAR. !
4 The margin of safety as defined in any Technical Specification is not reduced by this purely -
a administrative change. :
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1996 ANNUAL OFERATING REPORT EDWIN I. IIATCH NUCLEAR PLANT BASES CHANGES i
B 3.6.2.1, Unit 1 Rev.11 and Unit 2 Rev.12 This change adds a paragraph to the Bases describing how average suppression pool temperature is obtained when some of the temperature monitoring channels are out of service. This revision to l the Bases does not alter the function or maintenance of any system designed to prevent or j mitigate the consequences of any type accident. The change only references a long-standing l procedural method for calculating suppression pool temperature if some monitoring channels are ,
inoperable. I The average suppression pool temperature can be reasonably obtained even if some of the temperature monitoring channels are out of service. Depending on the number of channels out of :
service, a correction factor may Fe applied to ensure a conservative value is calculated for : .
temperature. This ensures suppression pool accident analyses assumptions are met. Therefore, the probability ofincreasing the consequences of an accident are not increased. Additionally, the Technical Specifications margin of safety is not reduced since this allowance does not conflict !
with the Technical Specifications minimum number of required channels t
Unit 1 Rev. 8, Unit 2 Rev. 9
- 1. Unit I and Unit 2 B 3.3.4.2, ATWS-RPT Instrumentation, Applicable Safety Analyses, LCO, and Applicability a.
- 2. Unit 1 B 3.1.4 '
- 3. Unit 1 and Unit 2 B 3.3.5.1, ECCS Instrumentation, Actions for B.I. B.2, and B.3
- 4. Unit I and Unit 2 B 3.7.6, Main Condenser Offeas, SR 3.7.6.1
- 5. Unit 2 B 3.5.1 ECCS-Operatine, Background These administrative changes are as follows. Change No. I provides appropriate wording, eliminating incorrect wording, to reflect a design change. Change No. 2 corrects a typographical error. Change No. 3 captures a GPC commitment in the Bases which requires actions more conservative than those required by the wording of the Technical Specifications. Change No. 4 I corrects an error made in transition to Improved Technical Specifications. Change No. 5 corrects l
wording which was inadvertently changed in a subsequent revision. These changes do not afTect J the probability or consequences of an accident or malfunction evaluated in the FSAR and do not l create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR. These administrative changes do not reduce the margin of safety as )
defined in the basis for any Technical Specification.
j Unit 1 Rev. 8, Unit 2 Rev. 9 B 3.3.3.1 PAM Instrumentation, LCO for Function No. 9. Suppression Pool Water Temperature These changes are administrative, i.e., changing two words in the Bases to accurately reflect plant design and the description provided in the FSAR. These changes do not afTect the probability or consequences of an accident or malfunction evaluated in the FSAR and do not create the l
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT BASES CIIANGES possibility of an accident or malfunction of a difTerent type than any previously evaluated in the FSAR, nor reduce the margin of safety as defined in the basis for any Technical Specification.
SR 3.8.1.15. Unit 1 Rev. 7. Unit 2 Rev. 8 The Bases for Technical Specifications SR 3.8.1.15 referenced SR 3.8.1.10. That portion of SR 3.8.1.10 that was referenced was deleted per NUREG 1433 Comparison Document Justification for Deviation. The inappropriate reference to 3.8.1.10 in Units 1 and 2 SR 3.8.1.15 was removed.
This administrative change does not afrect the probability or consequences of an accident or malfunction evaluated in the FSAR and does not create the possibility of an accident or malfunction of a difTerent type than any previously evaluated in the FSAR. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
B 3.3.5.2. Unit 1 Rev. 6 For a description of this change, reference the discussion for DoCR 96-06.
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCll NUCLEAR PLANT UNIT 1/ COMMON TRM CHANGES Table T5.0-1, Unit 1 Rev. 7. Unit 2 Rev.10 This administrative change lists SAFER /GESTR (DBA LOCA analysis) valve times in a convenient location. The closing times for valves 1/2B31-F031A&B,1/2El F015A&B, and 1/2E21-F005A&B are listed in Table T5.0-1. No changes to any requirements were made. Since ,
this change only provides needed information, it does not increase the probability or consequences of an accident or malfunction previously evaluated in the FSAR and does not create the possibility I of an accident or malfunction of a different type than any previously evaluated in the FSAR. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
Table T6.0-1. Table T7.0-1 Table T10.1-1, and Table T10.2-1, Unit 1 Rev. 6
- For a description of this change, reference DoCR 96-06.
Unit 1 T11.0 Loss of Function Diagrams: LFD-1-ECCS-01, LFD-1-ECCS-05, LFD-1-ECCS-12, LFD-1-ECCS-18 LFD-1-MCREC-02, LFD-1-RCIC-01, and l LFD-1-RPT-03. Also, Table TIO.1-1 (Sheet 4), and Table T10.2-1 (Sheet 18)
For a description of this change, reference DoCR 96-09.
T 8.3, Unit 1 Rev 6, Unit 2 Rev. 9. Secondary Containment Expansion This administrative change removes a phrase from T 8.3 to allow alternate methods of l determining the limiting combination of SGT for seconda:v containment expansion. This change l does not alter any plant structures, systems, components, or plant operation. This change does !
not affect the probability or consequences of an accident or malfunction evaluated in the FSAR and does not create the possibility of an accident or malfunction of a difTerent type than any previously evaluated in the FSAR This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
T3.7.2, Uni, ; Rev. 6, Unit 2 Rev. 9, ECCS and RCIC Room Coolers This is an administrative change to the Completion Time for Condition A of TRM T 3.7.2. This change is to clarify that the Completion Time refers to the discovery of an inoperable diesel generator for the oppasite division room cooler in the same diagonal room as the inoperable cooler which caused entry into Condition A. This change does not affect the probability or consequences of an accident or malfunction evaluated in the FSAR and does not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCil NUCLEAR PLANT UNIT 1/ COMMON TRM CIIANGES l
Table T7.0-1, Unit 1 Rev. 7. Unit 2 Rev.10 l
l Table T7.0-1 is revised to remove several of the valve operational time limits because they are not !
specifically required to ensure containment isolation by any accident, transient, or HELB analyses.
These valves are tested for operational functionality as part of the Plant Hatch Pump and Valve Inservice Test Program. The time limits will be retained in Table T7.0-1 for valves that are required to operate in a specific time by any accident, transient, or HELB analyses. Valve stroke times assumed in the SAFER /GESTR analysis will be provided in Section 5 of the TRM. Valves required to function to assure proper actuation of the ECCS will have their time limits provided in the appropriate sections of the FSAR.
This change does not alter any plant structures, systems, or components, or plant operation. This change does not affect the probability or consequences of an accident or malfunction evaluated in the FSAR and does not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
Table T7.0-1. Unit 1 Rev. 7. Unit 2 Rev.10 This administrative change brings the table into agreement with the Technical Specifications Bases to ensure consistency throughout the table and correct typographical errors. There is no change to plant structures, systems, or components, or to plant operation. This change does not afTect the probability or consequences of an accident or malfunction evaluated in the FSAR and does not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
l Table T7.0-1, Unit 1 Rev. 7 This is an administrative change to modify the listed inboard and outboard barriers of several j penetrations to reflect the actual physical status of and testing requirements for these barriers as provided in Unit 1 FSAR Table 7.3-1. This change does not alter any plant structures, systems, or components, or plant operation. This change does not afTect the probability or consequences of an accident or malfunction evaluated in the FSAR and does not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR. This administrative change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCil NUCLEAR PLANT UNIT 1/ COMMON TRM CilANGES T.2.1-1. Operability details for LCO 3.7.4, MCREC System, and 3.7.5. Control Room AC !
System. Unit 1 Rev. 9. Unit 2 Rev.12 This change revises the wording of footnote "d" of LCO 3.7.4 to clarify the action to be taken !
when a main control room AC subsystem is out of service an_d outside air temperature is less than 65"F.
The proposed change does not cause an increase in the probability or consequences of any type !
event and does not decrease the margin of safety, because the intent of the footnote is not being changed; the change is being made only to clarify meaning. Furthermore, the MCREC System '
will not be operated in a manner contrary to the FSAR as a result of this revision.
f Table T10.1-1, Unit i Rev. 9
- This change revises Table T10.1-1 to reflect the replacement of three radwaste discharge flow instruments with newer instruments.
This change reflects the change made and justified under DCR 90-110. The new radwaste ;
instruments meet existing FSAR requirements. The new instruments meet the requirements of ;
codes and standards which preclude the possibility of this equipment affecting any other safety-related system or component For these reasons, the probability of, and consequences of any type
- event, is not increased by the replacement of the instruments and the accompanying TRM change.
- No safety limim or limiting safety system setpoints are affected by the change. Therefore, the 1
) margin of safety as defined in the basis for any Technical Specifications is not reduced.
l' TLCO 3.4.2 Unit 1 Rev. 8. Unit 2 Rev.11
, This change revises TLCO 3.4.2, Structural Integrity, to clarify the scope of the TLCO as
- applying to ASME Code Class 1, 2, and 3 components per ISI boundary diagrams. Other changes for Code Class 2 and 3 components add restrictions on applicability of the TLCO, and allowances for declaring systems inoperable rather than immediate component isolation. This change allows the pursuit of temporary relief from the NRC for Class 3 components and 30 days to perform code repair of Class 3 components. A note is added to allow separate entry for each component.
The addition of the words "ISI boundary diagrams" to the TLCO Applicability is only for clarification and, thus, does not e!ier the maintenance or operation of plant equipment.
None of the remaining chan;;es to the Code Class 3 components affect the maintenance or
, operation of any plant component or equipment important to safety; therefore, the probability or consequences of any type event is not increased. Furthermore, the operability of each affected component will continue to be assessed and any required ACTION statements will be entered.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCH NUCLEAR PLANT l l
UNIT 1/ COMMON TRM CHANGES l i
The margin of safety as defined in the basis for any Technical Specification is not affected by these changes.
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCII NUCLEAR PLANT UNIT 2 TRM CIIANGES 4
Table T7.0-1. Rev.10 This administrative change ensures consistency throughout the table with the Local Leak Rate Test Program. This change does not alter any plant structures, systems, or components, or plant operation. This change does not affect the probability or consequences of an accident or malfunction evaluated in the FSAR and does not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR. This administrative l
change does not reduce the margin of safety as defined in the basis for any Technical Specification. l i
j Table T7.0-1. Rev.10 l l
This change removes the Type C testing requirements listed for penetrations 30A and 31A, because the configuration of these penetrations meets the requirements of Regulatory Guide 1.11 and are, thus, exempt from Appendix J, Type C testing requirements. These penetrations are tested during the Type A test. This change does not alter any plant structures, systems, or components, or plant operation. This change does not affect the probability or consequences of an accident or malfunction evaluated in the FSAR and does not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR. This change does not reduce the margin of safety as defined in the basis for any Technical ;
Specification. '
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1 1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCH NUCLEAR PLANT
! UNIT 1/ COMMON MINOR DESIGN CllANGES 94-5029 This change removes the low level hotwell trip to the three condensate pumps from level switch IN21-R026 and modifies the operation of this system by disabling the automatic condensate !
i pump trip due to low level in the hotwell as sensed by level switch IN21-R206. An annunciator will alert operations personnel if action will need to be taken to manually trip the condensate
- pumps.
The equipment is not safety related. Removing the pump trips does not prevent the plant from i being operated or shut down safely. This change does not reduce the margin of safety as defined 4
in the basis for any Technical Specification.
95-5002
) This change reroutes the HPCI discharge line vent and provides a permanent personnel access i platform to operate the HPCI vent valves to delete a personnel safety hazard. This modification has no impact on HPCI System operation.
The HPCI System is safety related. The platform modification is not safety related and has no adverse effect on the HPCI System because it meets applicable seismic requirements. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
95-5069 This change provides a local indication of high-pressure turbine first-stage pressure via a digital indicator to allow performance engineers to monitor heat rate more closely. No direct indication of first-stage pressure was previously available. This change does not modify the operation of the i main turbine.
1 The indicator is not safety related. The change does not affect operation of the main turbine. i This change does not reduce the margin of safety as defined in the basis for any Technical '
Specification.
96-5031 This change replaces specified instrument sump level switches to make the switches the same on both units, maintenance less complicated, and makes instruments more user friendly. This change does not modify the operation of this system.
The switches are not safety related. This change does not have an adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCII NUCLEAR PLANT UNIT I/ COMMON MINOR DESIGN CIIANGES 96-5040 This change deletes obsolete area radiation monitor 1D21-R900 in the main control room.
Monitoring performed by the recorder is performed by the SPDS which also records the radiation levels monitored.
The recorder is not safety related. Deleting the recorder has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT UNIT 2 MINOR DESIGN CilANGES 93-5052 This change replaces a temporary wall in the Unit 2 Radwaste Building to provide an area for snubber testing and ieduce combustible loading in the area.
No safety-related change is involved in this MDC. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
1 96-5032 1 This change replace:; PSW check valves 2P41-F306A/B with piping to prevent the occurrence of
, a failure which could limit cooling water flow to the PSW and RHRSW lube oil coolers. The valves prevent reverse flow in the piping system; they are not required by design since the line discharges to the river.
L The valves are safety related. The change removes a potential adverse effect (i.e., limiting of cooling water flow) on the PSW and RHRSW Systems. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-5034 This change connects cables from ;he Mark V controls to the seal water controls to provide RFP ,
speed refereace for the Seal Water System. This allows the Seal Water System to operate in the l transient or the normal mode of operation as applicable.
The RFP Seal Water System is not safety related. This change has no adverse effect on the system. This change does not reduce the margin of safety as defined in the basis for any Technical l Specification.
96-5039 This change abandons the Unit 2 SPDS inverter and does not modify the operation of the system.
The SPDS will retain backup power from an existing security inverter.
The SPDS is not safety related. This minor modification has no adverse effect on any safety-related system or component. This change does not reduce the rnargin of safety as defined in the basis for any Technical Specification.
96-5044 4
This change removes pump suction relief valves on the RHR System that are not required per design. This change does not modify the operation of this RHR system, because overpressure Page 38
1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT UNIT 2 MINOR DESIGN CIIANGES protection is not needed when the systems are in service, and because procedures will provide necessary protection when removing pumps from service or keeping them removed from service.
The RHR System is safety related. The change has no adverse effect on the operation of the RHR System as described above. This change does not reduce the margin of safety as defmed in the basis for any Technical Specification.
96-5046 This change modifies the Condensate Booster Pump Lube Oil System to eliminate oil leaks and improve system operation when in standby.
The Condensate Booster Pump Lube Oil System is not safety related. The change has no adverse effect on the operation of any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN I. HATCH NUCLEAR PLANT TEMPORARY MODil'ICATIONS 1-96-03 This temporary modification disables the " Rod Drift" alarm for five control rods to allow the alarm to clear such that the annunciator can be restored to operable for the remaining rods.
Operation of the CRD System remains unchanged.
This temporary modification restores annunciation capability for the remaining rods. This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
1-96-08 This temporary modification removes a tornado vent and replaces it with a plywood panel so a power cable can be routed through it. This modification does not modify the performance of the secondary containment.
The tornado vent is safety related. The temporary modificati m will maintain the secondary containment. This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
1-96-11 This temporary modification disables the " Rod Drift" alarm for one control rod in addition to those disabled by temporary modification 1-96-3 to allow the alarm to clear such that the annunciator can be restored to operable for the remaining rods. Operation of the CRD System remains unchanged.
This temporary modification restores annunciation capability for the remaining rods. This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
1-96-12 This temporary modification bypasses permissive logic such that drywell and reactor building equipment and floor drain sump pumps can be started with the RPS bus de-energized. This temporary modification is done with no fuel in the vessel, and is made to allow pump operation should the need arise during refueling outage operations. '
The logic is safety related. The temporary modification has no adverse effect on any safety-related system or component. The logic being bypassed is not in the Technical Specifications; thus, the modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT l TEMPORARY MODIFICATIONS 1-96-13 I This temporary modification adds a jumper to disable the isolation function of 1G31-F004 from a high temperature in the non-regenerative heat exchanger to allow chemical decontamination of the ;
RWCU System during a refueling outage. This isolation signal is for protection of demineralizer resins. '
The isolation is safety related. The temporary modification does not have an adverse effect on RWCU isolation. This isolation signal is not a Technical Specification requirement; thus, the modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
1-96-14 This temporary modification modifies the battery load bank test breaker to defeat the breaker's trip function in order to defeat nuisance tripping during battery testing. This modification does not delete the protection afforded by the breaker because it also adds a properly sized fuse to sufliciently protect the cables in the battery load bank test circuit.
The breaker is safety related. The temporary modification has no adverse efTect on the cables being protected by the breaker. This modification does not reduce the margin of safety as defined l in the basis for any Technical Specification. l 1-96-19 This temporary modification installs temporary cooling water to the lZ41-B025 shift supervisor j area condenser to allow maintenance on a valve in the normal water supply line. This modification allows the cooler to remain operable for habitability considerations.
The condenser is safety related. This temporary modification has no adverse effect on the cooler.
This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
1-96-20 This temporary modification disables the " Rod Drift" alarm for one control rod to allow the alarm to clear such that the annunciator can be restored to operable for the remaining rods (i.e., ones which are not disabled from providing input to the alarm). Operation of the CRD System remains unchanged. '
This temporary modification restores annunciation capability for the remaining rods. This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL' OPERATING REPORT EDWIN 1. IIATCil NUCLEAR PLANT TEMPORARY MODIFICATIONS 1-96-24 This temporary modification bypasses point 23 (pump B motor bearing closed cooling water) on recorder IB31-R601 to clear annunciator " pump motor A/B temp high" such that the remaining 21 points on recorder IB31-R601 can be alarmed on the recorder. Point 23 failed upscale, and its failure could mask the alarm condition of any of the remaining 21 points.
The recorder is safety related. The temporary modification has no adverse effect on any safety-related system or component. This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
1-96-25 This temporary modification changes the control circuits for both Unit I drywell floor drain sump pumps to allow automatic operation of the "A" pump (lGil-C001 A) from the controls for the "B" pump (lG11-C001B). The "B" pump will only have manual start and stop capability. While this modification is in place, the "A" pump will have all normal functions available. This temporary modification is necessary due to instrumentation problems associated with the pumps.
The instrumentation is nonsafety related, but is treated as safety related. This temporary '
modification maintains compliance with Unit 1 Technical Specifications LCO 3.4.5.a., and thus, does not reduce the margin of safety as defined in the basis for any Technical Specification.
1-96-40 This temporary modification replaces the normal supply breaker for Diesel Building MCC IB (IR24-S026) with a new breaker with type TSG (T) Static Trip II device to provide optimum coordination with downstream breakers. :
l The breaker is safety related. This temporary modification ensures proper functioning of the MCC; thus, it has no adverse efTect on any safety-related system or component. This ;
modification does not reduce the margin of safety as defined in the basis for any Technical i Specification.
1-96-41 This temporary modification modifies Diesel Building MCCs 1R24-S026 and IR24-S048 to eliminate a possible miscoordination between downstream nonsafety-related feeder breakers and the safety-related breaker for 1R24-S026 for certain postulated faults. The inodification includes moving one nonsafety-related load, disabling the tripping device for the normal supply breaker to IR24-S026, and resetting phase overcurrent relays. This temporary modification maintains the proper function of the MCCs.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCil NUCLEAR PLANT TEMPORARY MODIFICATIONS The MCCs are safety related. This temporary modification ensures proper functioning of the MCC; thus, it does not adversely impact any safety-related system or component. This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
2-96-08 This temporary modification removes the cable from channel 16 of the loose parts monitor to eliminate a spurious alarm from a sensor with damaged wiring. This modification restores alarm capability for the remaining 15 channels. The spurious alarm was evaluated as not being indicative of pump vibration.
The loose parts monitor is not safety related. This temporary modification has no adverse effect on any safety-related system or component. This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
2-96-12 This temporary modification raises the alarm setpoint for the "B" and "H" SRVs tailpipe temperature from 225aF to 275aF. This modification restores operability of the recorder for all 11 SRVs.
The recorder is safety related. This temporary modification restores operability of the recorder.
This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
2-96-14 This temporary modification replaces temporary modification 2-96-12. It raises the alarm setpoint for the "H" SRV tailpipe temperature from 275cF to 300 F and maintains the setpoint for the "B" SRV at 275'F. This temporary modification restores operability of the recorder for all 11 SRVs.
The recorder is safety related. This temporary modification restores operability of the recorder.
This modification does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT SETPOINT DESIGN CIIANGES 96-6004 This change modifies the setpoint for recorder 1B21-R614 (feeds the " Safety / Blowdown Valve .
Leaking" annunciator) from "230 degrees F" to "as directed by Operations Procedure ' Safety Blowdown Valve Leaking Annunciator Setpoint Change'" This change does not modify the .
function of the annunciator, but allows its setpoint to be procedurally controlled in case ofleaking valves. This change maintains the basis function of the alarm (i.e., to provide the operator with sufficient indication to maintain proper operating conditions).
The recorder is safety related. This change does not reduce the margin of safety as defined in the brsis for any Technical Specification because the alarm setpoint is not in the Technical Specifications, and has no active safety function.
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1996 ANNUAL OPERATING REPORT EDWIN I. HATCH NUCLEAR PLANT DOCUMENT CHANGE REQUESTS 96-01 This change modifies the Unit I and Unit 2 Technical Specifications Bases to address the changes made by DCRs94-007 and 94-008; and a proposed Technical Specifications change to Units 1 and 2 concerning the modifications to the PRNM and the installation of the OPRM. The Technical Specifications Bases change does not modify the operation of this system. The implementation of this change is contingent upon the NRC's approval of the Unit I and Unit 2 Technical Specifications change. '
This Technical Specifications Bases change concerning the PRNM and OPRM has no adverse effect on any safety-related system or component. This change does not reduce the margin of r safety as defined in the basis for the proposed Technical Specification.
96-03 This change modifies the Unit I and Unit 2 Technical Specifications Bases to allow them to address the changes made by Unit 1 Technical Specifications Amendment 201 and the Unit 2 Technical Specifications Amendment 142 concerning the drywell air temperature. This change does not modify the operation of this system. :
This Technical Specifications Bases change concerning the drywell air temperature has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-04 f
This change modifies the Unit I and Unit 2 TRMs concerning structural integrity to allow additional actions to be taken for certain conditions and to clarify the applicability of structural !
integrity requirements. This change does not modify the function of any system. (Reference Unit 1/ Common TRM Changes, TLCO 3.4.2, Revs. 8 and 1I for further discussion.) ,
This TRM structural integrity change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification. ,
f 96-05 This change clarifies the Unit 1 and Unit 2 FSAR descriptions of refueling operations to clearly define that normal refueling operations could consist of either a full core off-load or a fuel shufile. This change does not modify the function of any system.
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1996 ANNUAL OPERATING REPORT EDWIN I. HATCH NUCLEAR PLANT DOCUMENT CHANGE REQUESTS This FSAR refuehng operations description change has no adverse effect on any safety-related system or component. This change does nc,t reduce the margin of safety as defined in the basis for any Technical Specification.
96-06 This change modifies the Unit 1 TRhi and the Unit 1 Technical Specifications Bases to address the changes made by DCR 94-033 concerning modifications to safety-related h10Vs. The TRhi !
and Technical Specifications Bases change does not modify the operation of any system.
This TRhi and Technical Specifications Bases change has no adverse effects on any safety-related !
system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
I 96-07 i
This change modifies FHA Appendix B concerning to whom Special Reports for Fire Protection Program Deficiencies are required to be submitted. This change requires no physical alteration to any plant equipment or structure. The operating and surveillance requirements of fire protection systems are not changed. The analysis of fire hazards is not affected. This change does not modify the function or operation of any system. 1 i
This FHA Appendix B change has no adverse effect on any safety-related system or component.
This change does not reduce the margin of safety as defined in the basis for any Technical l Specification.
l 96-08 This change modifies FHA Appendix B to address the changes made by DCR 94-044 concerning modifications to emergency lighting and the addition of a fire door. This change does not modify the function of any system.
This FHA Appendix B change has no adverse effect on any safety-related system or component.
This change does not reduce the margin of safety as dermed in the basis for any Technical Specification.
96-09 This change modifies the Unit i TRhi to address the changes made by DCR 94-048 to decrease the probability of an RPT following a scram. The TRhi change does not modify the operation of any system.
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i 1996 ANNUAL OPERATING REPORT EDWIN L IIATCH NUCLEAR PLANT DOCUMENT CilANGE REQUESTS !
This TRM change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
i 96-12 This change is for the Unit 1 Cycle 17 COLR, Revision 0. The APLHGR cmves are revised to reflect cycle-specific fuel types, and the MCPR Operating Limit values are revised as a result of the Cycle 17 reload licensing analysis. This change does not modify the function of any system.
The issuance of the Unit 1 Cycle 17 COLR, Revision 0 has no adverse effect on any safety-related j system or component. All values stated in the COLR are calculated using NRC-approved codes and standards. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
j 96-13
. This change modifies the Unit I and 2 TRM and the Unit I and 2 Technical Specifications Bases
- concerning various editorial changes. This change does not modify the function of any system.
j This Unit I and 2 TRM and the Unit I and 2 Technical Specifications Bases change has no l adverse effect on any safety-related system or component. The change does not reduce the margin of safety as defined in the basis for any Technical Specification.
4
- 96-14 This change modifies the Unit 2 FSAR concerning the description of the EHC hydraulic power supply. This change does not modify the function of any system.
This FSAR EHC hydraulic power supply description change has no adverse efTect on any safety-related system or component. This change does not reduce the margin of safety as defmed ;
in the basis for any Technical Specification.
96-15 This change is for the Unit 1 Cycle 17 COLR, Revision 1. This change does not modify the function of any system.
The issuance of the Unit 1 Cycle 17 COLR, Revision 1 has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
Page 47
1993 ANNUAL OPERATING REPORT EDWIN 1. IIATCil NUCLEAR PLANT DOCUMENT CIIANGE REQUESTS 961.6 This change modifies the Unit 1 and Unit 2 Technical Specifications Bases to allow them to address the changes made by Unit 1 Technical Specifications Amendment 202 and the Unit 2 Technical Specifications Amendment 143 concerning the CST levels. This change does not modify the operation of this system.
This Technical Specifications Bases change concerning the CST levels has no adverse efTect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-17 This change modifies the Unit 2 FSAR concerning the description of who administrates the SAER finding and NRC violation trending. This change does not modify the function of any system.
This FSAR trending description change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-19 This change modifies the Unit I and 2 TRM concerning the Loss of Function Diagrams associated with the APRM functions. This change does not modify the function of any system.
This Unit I and 2 TRM change has no adverse efTect on any safety-related system or component.
The change does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT DOCUMENT CIIANGE REQUESTS 96-20 This change modifies the Unit I and 2 Technical Specifications Bases concerning PAM instrumentation description, RPV water level ATWS-RPT level description, and various other changes. This change does not modify the function of any system.
This Unit I and 2 Technical Specifications Bases change has no adverse effect on any safety-related system or component. The change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-21 This change modifies the Unit I and 2 TRM concerning acceptance criteria and primary containment isolation devices. This change does not modify the function of any system.
This Unit 1 and 2 TRM change has no adverse effect on any safety-related system or component.
The change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-22 This change modifies the Unit I and 2 TRM concerning a clarification of when an AHU is required to be declared inoperable. This change does not modify the function of any system.
This Unit I and 2 TRM change has no adverse effect on any safety-related system or component.
The change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-23 This change modifies the Unit I and Unit 2 Technical Specifications Bases to allow them to address the proposed changes made to the Unit 1 and Unit 2 Technical Specifkaiians concerning RCS Pfr limits. This change does not modify the operation of this system. fhe i uplementation of this change is contingent upon the NRC's approval of the Unit I and Unit 2 Technical Specifications change.
This Technical Specifications Bases change concerning the RCS P/T limits has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for the proposed Technical Specification.
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1 1996 ANNUAL OPERATING REPORT EDWIN I. IIATCil NUCLEAR PLANT DOCUMENT CIIANGE REQUESTS l
96-26 ,
This change modifies the Unit 2 FSAR concerning the description of the plant organization with
)
regard to performance teams. This change does not modify the function of any system.
l This FSAR plant organization description change has no adverse effect on any safety-related ;
system or component. This change does not reduce the margin of safety as defined in the basis i f >r any Technical Specification. :
96-28 This change modifies the Unit I and Unit 2 Technical Specifications Bases concerning the clarification of how the suppression pool average water temperature is determined. This change does not modify the operation of this system. (Reference Bases Changes, B 3.6.2.1, Revs. I1 and 12 for further discussion.)
This Technical Specifications Bases change concerning the clarification of how the suppression pool average water temperature is determined has no adverse effect on any safety-related system or compon nt. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-29 This change modifies the Unit 1 TRM to address the changes made by DCR 90-110 concerning modifications to radwaste discharge flow instrumentation. The TRM change does not modify the operation of any system. (Reference Unit 1/ Common TRM Changes, Table T10.1-1 for funher discussiori.)
This TRM change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-31 This change modifies the Unit I and Unit 2 Technical Specifications Bases to address the proposed changes made to the Unit 1 and Unit 2 Technical Spec 5 cations concerning SRV j setpoint changes. This change does not modify the operation of this system. The implementation l of this change is contingent upon the NRC's approval of the Unit I and Unit 2 Technical Specifications change. ;
This Technical Specifications Bases change concerning SRV setpoint changes has no adverse
- efTect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis of the proposed Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN I. IIATCil NUCLEAR PLANT DOCUMENT CIIANGE REQUESTS j 96-33 .
l This change modifies the Unit 2 TRM to address the change made by DCR 92-134 concerning the modification to relocate the drywell return air fan motor to a difTerent compartment. The TRM change does not modify the operation of any system.
This TRM change has no adverse efTect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis for any Technical Specification.
96-35 This change modifies the Unit 2 Technical Specifications Bases to address the proposed changes made to the Unit 2 Technical Specifications concerning Safety Limits. This change does not modify the operation of this system. The implementation of this change is contingent upon the NRC's approval of the Unit 2 Technical Specifications change.
1 This Technical Specifications Bases change concerning the Safety Limits change has no advers; effect on any safety-related system or component. This change does not reduce the margin of safety as dehed in the basis of the proposed Technical Specification.
96-36 I l
This change modifies the ODCM concerning the interlaboratory comparison program. This change does not modify the operation of any system.
This ODCM change concerning the interlaboratory comparison program change has no adverse effect on any safety-related system or component. This change does not reduce the margin of safety as defined in the basis of any Technical Specification.
Page 51
1996 ANNUAL OPERATING REPORT EDWIN I. IIATCII NUCLEAR PLANT PLANT DEFICIENCIES This evaluation assessed an as-found condition where Unit 1 "B" RHRSW System heat exchanger and adjacent piping were found to be contaminated. The leak and any potential past or future release via the RHRSW System to an unrestricted area was evaluated. The evaluation concluded:
l 1) any release in no way presented a threat to the health and safety of a member of the public; 2) i any release did not exceed applicable limits; 3) any release did not constitute a Licensee Event
- l Report; 4) any release did not exceed 10 CFR 100 limits; 5) Design Criterion 64 of 10 CFR 50, Appendix A is satisfied; 6) 10 CFR 50, Appendix I is satisfied; 7) the requirements of NRC l Bulletin 80-10 are satisfied; and 8) operation of the RHRSW System is not adversely affected by ;
the leak.
The RHRSW System is safety related. The small amount of radioactive inleakage into the system does not affect proper system operation. Since limitations of Technical Specification 5.5.4 are met, this event does not reduce the margin of safety as defined in the basis for any Technical Specification.
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1996 ANNUAL OPERATING REPORT EDWIN 1. HATCII NUCLEAR PLANT PLANT PROCEDURES 34SO-C11-005-IS Revision 17 to the Control Rod Drive Hydraulic System operating procedure allows for flushing i the collet piston seals in accordance with the applicable vendor manual. This procedure temporarily changes the configuration of the HCU as described in the FSAR. Flushing is allowed only after an "all rods in" condition has been established. This revision does not modify the operation of this system because actions are taken to avoid possible rod withdrawd 1 Since no new modes of operation of the CRD System are being introduced, the proposed procedure revision does not reduce the margin of safety as defined in the basis for any Technical Specification.
34SO-C11-005-2S Revision 16 to the Control Rod Drive Hydraulic System operating procedure allows for flushing the collet piston seals in accordance with the applicable vendor manual. This procedure temporarily changes the configuration of the HCU as described in the FSAR. Flushing is allowed only after an "all rods in" condition has been established. This revision does not modify the operation of this system because actions are taken to avoid possible rod withdrawal.
l Since no new modes of operation of the CRD System are being introduced, the proposed +
procedure revision does not reduce the margin of safety as defined in the basis for any Technical ,
Specification.
34SV-C41-003-2S Revision 9 to the Standby Liquid Control Injection Test surveillance procedure allows for draining of the system directly to the chemical waste drain system instead of to 55-gal drums.
This is contrary to Unit 2 FSAR paragraph 4.2.3.4.2. The intent of the FSAR (i.e., not to allow I the liquid to enter reactor coolant) is still met because chemical waste would be properly treated -
prior to returning it to the CST. !
l l No margin of safety as defined in the basis for any Technical Specification is impacted by this !
j proposed revision. !
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1996 ANNUAL OPERATING REPORT EDWIN 1. IIATCII NUCLEAR PLANT I
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J DATA TABULATIONS AND UNIQUE REPORTING REQUIREMENTS I
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i 1996 ANNUAL OPERATING REPORT EDWIN 1. HATCH NUCLEAR PLANT OCCUPATIONAL PERSONNEL RADIATION EXPOSURE FOR 1996 ;
l This section satisfies the requirement of the Edwin I. Hatch Nuclear Unit I and Unit 2 Technical i Specification 5.6.1 and assures compliance with the Code of Federal Regulations. Special I attention was afforded to the methods prescribed by the Commission in Regulatory Guide 1.16 in !
order that the intent, as well as the letter of these laws, might be fulfilled with providing meaningful information as to the degree and circumstances of exposure of personnel at this ,
facility. An indication of the effectiveness of the plant radiation program may be inferred from the :
large number ofindividuals with no measurable exposure or minimal dose. !
The time peri d covered by this tabulation extended from January 1,1996 through December 31, 1996. Indivical exposures as indicated by Electronic Direct Reading Dosimeters (EDRDs) were recorded daily with the use of an ALARA Computer System. These exposures were tabulated and printed in hard copy on a daily basis and when required, along with the difference between these readings and the most restrictive exposure limit. The corresponding EDRD results, as recorded on the disc dosimetry files, were supplanted by thermo-luminescent measurements made over a period of approximately one calendar quarter as the data became available from a vendor.
It should be noted, however, that radiation exposure values presented herein were based on EDRD (estimated readings).
Each person listed in the dosimetry disc files was assigned a job category based on daily activities.
The six job categories are identified in the following table. Running totals of dose acquired in each of these categories were maintained for each person in his/her dosimetry file. Each dosimeter reading was added for individual exposure records and to the total representing the cumulative dose in the appropriate job category.
The implicit assumption involved in this method of accounting for exposure in different tasks is that all exposure acquired in job categories other than the usual will be documented by a Radiation Work Permit. This circumstance should prevail in all significant cases.
Further delineation regarding the number of persons and amount of exposure to individuals in '
different job categories and by various personnel categories is indicated by the standard reporting format of Regulatory Guide 1.16. Each peisonnel dosimetry disc file contains the personnel category information required to accomplish the record keeping. The individual running dose totals for eachjob were used by ALARA Computer to compute the number of man-rem indicated in each group. Backup disc files were maintained for redundancy in the case of destruction of temporary inaccessibility suffered by the files. Hard copy records as printed by the ALARA Computer were also maintained.
By the use of the ALARA Computer System, dosimetry information was compiled, retained and tabulated in such a manner as to satisfy the pertinent Federal Regulations and Plant Technical Specifications. The system has been organized to provide the information in the format specified by theses requirements and the suggestions of the Regulatory Guides.
Page 55
1996 ANNUAL OPERATING REPORT EDWIN 1. HATCil NUCLEAR PLANT REGULATORY GUIDE 1.16 INFORMATION END OF YEAR REPORT- 1996 Number of Personnel
> 100 mrem Total man-rem
- Work and Job Function Station Utility Contractor Station Utility Contractor ROUTINE PLANT MAIPrTENANCE MAINTENANCE AND CONSTRUCTION 185 6 339 109.824 2.215 130.059 OPERATIONS 15 0 0 5.995 0.000 0.009 HEALTH FHYSICS 8 0 22 2.917 0.000 8.956 SUPERVISORY 22 0 7 8.764 0.063 2.522 ENGINEERING 12 0 21 4.398 0.067 6.311 R0tTTINE OPERATIONS AND SURVEILLANCE MAINTENANCE AND CONSTRUCTION 9 0 3 4.852 0.107 4.108 OPEMTIONS 74 0 0 38.955 0.000 0.029 HEALTH PHYSICS 65 0 24 30.674 0.008 7.526 SUPERVISORY 11 0 3 4.008 0.040 0.849 ENGINEERING 3 0 0 2.354 0.082 0.442 INSERVICE INSPECTION MAINTENANCE AND CON 71R'7CTION 3 0 3 0.900 0.011 0.751 OPERATIONS 24 0 0 7.470 0.000 0.000 HEALTH PHYSICS 15 0 16 11.504 0.000 9.707 SUPERVISORY 3 0 0 0.833 0.089 0.000 ENGINEERING 1 0 13 0.444 0.021 4.192 SPECIAL PLANT MAINTENANCE MAINTENANCE AND CONSTRUCTION 69 0 96 25.649 0.021 36.207 OPERATIONS 5 0 0 1.100 0.000 0.000 HEALTH FHYSICS 5 0 16 0.891 0.000 10.480 SUFERVISORY 7 0 1 2.908 0.000 1.003 ENGINEERING 4 0 0 1.120 0.030 0.175 Page 56 i.+!.--_..---_
1996 ANNUAL OPERATING REPORT EDWIN I. HATCII NUCLEAR PLANT REGULATORY GUIDE 1.16 INFORMATION END OF YEAR REPORT- 1996 Number of Personnel 1 a 100 aren Total man-rem *
- Work and Job Function . Station Utility Contractor Station Utility Contractor WASTE PROCESSING MAINTENANCE AND CONSTRUCTION 6 0 0 1.460 0.030 0.045 OPERATIONS O O 1 0.017 0.000 0.223 HEALTH PHYSICS 4 0 4 2.688 0.000 3.205 S!!PFRVISORY 1 0 0 0.148 0.000 0.000 ENGINEERING 0 - 0 0 0.002 0.000 0.000 REFUELING OPERATION MAINTENANCE AND CONSTRUCTION 4 0 69 1.154 0.000 20.238 OPERATIONS 9 0 0 1.994 0.000 0.000
- HEALTH PHYSICS 0 0 0 0.000 0.000 0.089 SUPERVISORY 0 0 0 0.185 0.000 0.194 ENGINEERING ,
2 0 7 0.431 0.004 2.123 Totals MAIrrrENANCE AND CONSTRUCTION 276 6 510 143.839 2.384 191.400 OPERATIONS 127 0 1 55.531 0.000 0.261 HEALTH PHYSICS 97 0 82 48.674 0.008 39.963 ;
SUPERVISORY 44 0 11 16.846 0.192 4.568 !
ENGINEERING 22 0 41 8.749 0.204 13.243 [
Grand Totals 566 6 645 273.639 2.788 249.443
- The total radiation exposure of the above personnel constitutes 100% of the site's exposure for the year.
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