ML19264B529

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Amend 46 to License DPR-3,implementing Interim Tech Specs for Fire Protection Sys Transmitted on 771125
ML19264B529
Person / Time
Site: Yankee Rowe
(DPR-03-A-046, DPR-3-A-46)
Issue date: 02/28/1978
From: Schwencer A
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19264B528 List:
References
NUDOCS 8011170108
Download: ML19264B529 (41)
v • d • e


Text

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[p, pro UNITED STATES y~

1 NUCLEAR REGULATORY COMMisslON

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,g W ASHINGT ON, D. C. 20555 k.....,e YANKEE ATOMIC ELECTRIC COMPANY E

DOCKET NO. 50-29 YANKEE NUCLEAR POWER STATION (YANKEE-F0WE)

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. DPR-3 1.

The Nuclear Regulatory Comission (the Commission) has found that:

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A.

The application for amendment by Yankee Atomic Electric Company (the licensee) dated July 18, 1977, as supplemented December 14, 1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in confomity with the application t>.

the provisions of the Act, and the rules and regulations of the Corraission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and scfety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as ir.dicated in the attachment to this license amend ent, and paragraph 2.C.(2) of Facility Operating License No. DFR-3 is hereby amended to read as follows:

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(2) Technical Specifications The Technical Spcciilc_ations contained in Appendix A, as revised through Amendment No. 46, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

OR THE NU,' EAR REGULATORY COMMISSION

/akawc&v A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 28, 1978 e

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ATTACHMENT TO LICENSE AMENDMENT NO. 46 FACILITY LICENSE NO. DPR-3 DOCVF' 'es. 50-29 Revise Appendix A as follows:

Remove the following pages and insert revised pages:

III - IV B 3/4 7 3/4 7-8 Y - VI 6 6-E XI - XII 6 6-4 XIII - XIV 6 6-6 XV 6 6-8 3/43-27-3/43-28 6 6-10 3/47-31-3/47-32 6 6-12 3/47-33-3/47-34 6 6-14 3/4 7 3/4 7-35 6 6-22 B 3/4 3 B 3/4 3-2 Add the following new page:

21 Marginal lires indicate revised area. Overleaf pages are provided for convenience.

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i INDEX LIMITlHG CONDITI0f45 FOR OPERATION AND SURVEILLANCE REQUIREMEllTS Pace SECTION 3/4 0-1 3/4.0 APPLICABILITY.............................................

3/4.1 Rf ACTIVITY CONTROL SYSTLM S 3/4.1.1 BORATION CONTROL Shutdown Margin - T

> 330"f..........................

3/4 1-1 3yg Shutdown M argin - T

< 330 f..........................

3/4 1-3 avg 3/4 1-5 Boron Dilution.........................................

3/4 1-7 M oderator Temperature Coef ficient......................

3/4.1.2 BORAT10N SYSTE45 3/4 1-8 Dow Paths - Refueling.................................

3/4 1-9 now Paths Shutdcrin..................................

3/4 1-11 now Paths - Operating.................................

3/4 1-13 Charging Pumps - Refueling.............................

3/4 1-le Charging Pump - Shutdown...............................

3/4 1-15 Cha rgi ng Pumps - Opera ti ng.............................

Eoric Acid Mix Tank G ravity feed Connection - Shutdown 3/4 1-16 a n d i' e f u e l i n g........................................

Boric Acid

  • Mix lank Gravity feed Connection -

3/4 1-17 0perating............................................

Borated Water Sources -

Refueling......................

3/4 1-18 3/4 1-19 Boraicd Unter Sources - Shutdown.......................

Borated Water Sources - Operating.....................

3/4 1-21 3/4.1.3 fiOVADLE CONTROL RODS 3/4 1-23 Lontrol Pod Operability................................

3/4 1-25 Position Indicator Channels............................

3/4 1-26 R o d If r c p T i r c..........................................

Sh u t d own Ro d i n s e rtion L :'ai t...........................

3/4 1-27 Contral Rod Insertion Limits...........................

3/4 1-28 lYRELF-ROWE} Arendment No. 46

I INDEX j LIMITING CONDITIONS FOR E R AT I_,' AND SURVEILLANCE REQUIREMENTS SECTION Page 3/4.2 POWER DISTRIFUTION LIMITS 3/4.2.1 PEAK LINEAR HEAT GENERATION RATE......... 3/4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT CHANNEL FACTOR...... 3/4 2-7 3/4.2.3 WUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR.......... 3/4 Z-9 3/4.2.4 DNB PARAMETERS.................................. 3/4 2-11 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE SYSTEM INSTRUMENTATION... 3/4 3-1 3/4.3.2 ENGINEERED SAFEGUARDS SYSTEM INSTRUMENTATION.... 3/4 3-11 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation............... 3/4 3-17 Incore Detection System............................... 3/4 3-23 Meteorological Instrumentation... 3/4 3-24 Fire Detection Instrumentation.... 3/4 3-27 l 3/4.4 MAIN COOLANT SYSTEM 3/4.4.1 MAIN COOLANT LOOPS Narmal Operation......... 3/4 4-1 Isolated Loop. 3/4 4-3 1solated Loop Startup.. 3/4 4-4 3/4.4.2 SAFETY VALVES - SHUTDOWN.. 3/4 4-5 3/4.4.3 SAFETY VALVES - OPERATING............... 3/4 4-6 3/4.4.4 PRESSURIZER............................... 3/4 4-7 3/4.4.5 MAIN COOLANT SYSTEM LEAKAGE Leakage Detection Systems.... 3/4 4-8 Operational Leakage.......... 3/4 4-10 1 YANKEE-ROWE IV A"endment No. 46

I ( F INDEX LilillitM C0fDITIONS FOR OPERAT10!1 A!:D SURVEILLI.tCE REQUIREMENTS .P._AG. E_ SECT 10N 3/4 4 12 3/4.4.6 C H E f 11 S T R Y.............................................. 3/4.4.7 SPECIFIC AC11VITY...................................... 3/4 4-15 3/4.4.8 PRESSURE /TD;PERATURE LIMIls 3/4 4-19 lia i n C ool a nt Sy s tem.................................... 3/4 G 25 Pressurizer............................................ 3/4.4.9 STRUCTURAL INTEGRITY................................... 3/4 4-26 3/4.5 EMERGENCY CORE C001.It:G SYSTDiS ((CCS) 3/4 E-1 3/.. 5.1 ACCU".ULAT0R............................................ 3/ /: 'O ?/ 6. 5. 2 l CCS Si O SY Si E F.S........................................ 3/6 f-9 3/4.5.3 ECCS SUT.3YSTn'.E...................... -3/ /. 5-11 5/3.5./ S 6 F L l Y 1 U E CT I D:i T Ar..'..................................

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' Y ST' a ./4.0.1 PRI!',ARY CONTAIN'iFNT 3/4 6 l Containment Intt9rity.................................. 3/4 6-2 Containment Icaktge.................................... 3/4 6 / C e r ' e i n,..: n t Ai r 1 0 c1:................................... 3/4 i-5 1 I n t e r n a l l' r e s t, u re...................................... 3/ 4 C-6 A i r T e m;, e r a t u r e........................................ Contoinment Vessel Structural Integrity................ 3/4 6-7 Continuous Leok Honitoring System...................... 3/4 6-0 3/4.6.2 CO*:T AI RMEllT I SOL AT ION V ALVES........................... 3/4 6-9 YANEEE-ROWE V Amendment No, 46

INDEX f: LIMITING CONDITIONS FOR OPERATION AND SURVETLLANCE REQUIREMENTS PAGE SECTION 3/4.6.3 COMBUSTISLE GAS CONTROL 3/4 6-16 Hydrogen Analyzer................................. 3/4 6-17 Hydrogen Vent System................................... Atmosphere Reci rculation System............... 3/4 6-18 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE 3/4 7-1 Safety Valves......... 3/4 7-5 Emergency Boiler Feedwater System...................... Primary and Demineralized Water Storage Tanks.. 3/4 7-6 3/4 7-7 A c t i v i ty..................................... Turbine Generator Throttle and Control Valves.......... 3/4 7-9 Secondary Water Chemistry........................... 3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........ 3/4 7-13 3/4.7.3 PRIMARY PUMP SEAL WATER SYSTEM....................... 3/4 7-14 3/4.7.4 SERVICE WATER SYSTEM................................... 3/4 7-16 3/4.7.5 CCNTROL ROOM VENTILATION SYSTEM EMERGENCY SHUTDOWN... 3/4 7-18 ?/4.7.6 SEALED SOURCE CONTAMINATION............................ 3/4 7-19 3f4. 7. 7 WASTE EFFLUENTS Radioactive Solid Waste........... 3/4 7-21 R a di o a cti ve Li quid Waste............................ 3/4 7-22 Radioactive Gaseous Waste......... 3/4 7-23 3/4.7.8 ENVIRONMENTAL MONITORING.................. 3/4 7-24 3/4.7.9 SHDCK SUPPRESSORS (SNUfDERS)........................ 3/4 7-27 3/4 7.10 FIRE SUPPRESSION SYSTEMS............................... 3/4 7-31 3/4 7.11 PENETRATION FIRE BARRIERS.......................... 3/4 7-36 VI Amendment No 46 YANKEE-ROWt i

( INDEX BASES _SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CON.AINMENT............................ B 3/4 6-1 3/4.6.2 CONTAINMENT ISOLATION VALVES................... B 3/4 6-3 3/4.6.3 COMBUSTIBLE GAS CONTROL........... B 3/4 6-3 3/4.7 PLANT SYSTEMS 3/4.7.1 TUR3INE CYCLE................... D 3/4 7-1 3/4.7.2 STEAh GENERATOR PRESSURE /TEMERATURE LIMITATION..... B 3/4 7-4 3/4.7.3 PRIMARY PUMP SEAL WATER SYSTEM...................... B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM....................... B 3/4 7-4 3/4.7.5 CONTROL ROOM VENTILATION SYSTF" EMERGENCY SHUTDOWN.. B 3/4 7-4 3/4.7.6 SEALED SOURCE CONTAMINATION..... B 3/4 7-4 B 3/4 7-5 3/4.7.7 Va.STE EFFLUENTS............................ B 3/4 7-6 3/4.7.8 ENVIRONMENTAL MONITORING.................... 3/4.7.9 SHOCK SUPPRESSORS (SNUBBERS)............ B 3/4 7-6 3/4.7.10 FIRE SUPPRESSION SYSTEMS.. B 3/4 7-8 3/4.7.11 PENETRATION FIRE BARRIERS............. B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS B 3/4 8-1 3/4.8.1 A.C. SOURCES........ 3/4.8.2 CNSITE POWER DISTRIBUTION SYSTEMS. B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTIVITY... B 3/4 9-1 3/4.9.2 INSTRUMENTATION. B 3/4 9-1 YANKEE-R04E XI A"endment No. 46

INDEX r BASES PAGE SECTION 3/4.9.3 DECAY TIME.............................................. B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS....................... B 3/4 9-1 3/4.9.5 COMMUNICATIONS.......................................... 0 3/4 C-1 3/4.9.6 SHIELD TANK MANIPULATOR CRANE OPERABILITY.............. B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT.......................... B 3/4 9-2 3/4.9.8 COOLANT CIRCULATION.................................... B 3/4 9-2 3/4.9.9 CONTAll: melit PURGE FAN SHUTDON!! SYSTEM.................. B 3/4 9-2 53/4.9.10 and 3/4.9.11 !!ATER LEVEL-RET.C OR YESSEL At;D SPEllT FUEL l PIT.................................................... D 3//. c-2 1 '3/4.9.12 SPENT FUEL PIT CUILDIG ISCL/Ji10'!...................... D './ ', m ' ' '/,.10 SPEC!!J 1FST D'CFP7IC"3 3/4.10.1 S l !U T L D;lN M AR G I !!........................................ f 3//. iG-1 3/4.10.2. CD:!TnDL RCD CPERABILITY A!:0 INSERTIC t LIf1ITS........... B 3/4 10-1 3/4.10.3 FRESSUE/it.rERATO E LIMITATic:is-REl.CTC.~1 Ci!!T I C ALI TY..... B 3/ -' l bi 3/4.10.4 PHYSICS TE515.......................................... S 3/'. 10-1 YAt0:EE-ROWE XII Amendment No. 46

( IfiDEX DESIGN FEATURES u PAGE SECTION 5.1 SITE' 5-1 Exclusion Area............................................... 5-1 Low Population Zone.......................................... 5.2 CONTAINMEllT 5-1 Configuration................................................ 5-1 Design Pressure and Temperature.............................. 5.3 Er_ ACTOR CORE 5.-1 T e c1 A s s e r.bl i e r............................................... S '. Control Rods................................................. t; '. 3.4 'RIN COOL A'P SYT7! T t t 5.> D e s i gn P re s s u r e e nd Tenp eri. t u r e.............................. E '. YO)'vId....................................................... g t2 b4 l3.5 i-ji T 10_L E O T Q Q 0 CATI (q................................ I f f.l,__L y!m..- ,3.O ..U. at 5-5 Criticality................................................ 5-5 Drainage.................................................... 5-5 Capacity.................................................... 5-5 5.7 COMPONENT CYCLI C OR TRANSIEliT LIM 1T......................... YANKEE-R0h'E XIII Amendment No. 46

f INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY.............................. 6-1 6.2 ORGANIZATION Offsite.................................. 6-1 Facility Staff........ 6-1 6.3 FACILITY STAFF QUALIFICATIONS........................ 6-6 6.4 TRAINING..... 6-6 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATION REVIEW COMMITTEE 6-6 Function................................ Composition. 6-7 Al+ernates.................... 6-7 Meeting Frequency....................... 6-7 Quorum. 6-7 Responsibilities.. 6-7 Authority...... 6-8 Records.......................................... 6-9 l 6.5.2 NUCLEAR SAFETY AUDIT AND REVIEW COMMITTEE Function.. 6-9 Composition.. 6-9 Qualification.............. 6-9 Alternates.... 6-10 YANKEE-ROWE XIV Amendment No. 46

( l.- ADMIfilSTRATIVE CONTROLS SECT 10i1 PAGE Co n s ul t a n t s............................................ 6-10 6-10 Meeting Frequency...................................... 6-10 Quorum................................................. 6-11 Review................................................. 6-11 Audits................................................. 6.-12 Authority.............................................. 6-12 Records................................................ 3.5.3 INDEPE!) DENT I.UDIT Af1D REV1EM......................... 6-12 5.6 REPnRTACl.E OCCURREl:CE ACTION........................... ,6-13 6.7 SAFETY LIMIT V101.AT10N................................. 6-13 3.8 PROCEDURES............................................. 6--13 5.9 PJ %9TI!iG r.EQU1NMENTS ' D.1, 6.9.2, 6.9.3 ROUTINE REP 0RTS........................ 6-M 5.9.4 REPORlABLE CLCURRENCES........................ 6116 5.9.5 Dii10UE REPORll!$ REQUIREMENTS............ 0 -l G 6.9.6 SPECIAL REP 0RTS...................................... 6-cl 6.10 R t CORD RE T E l:T 101...................................... 6-22 5.11 RADIA110N PP,0TEC110N PR0 GRAM.......................... 6-23 6.12 RESPIRATORY PROTFCTION PROGRAM 5.12.1 ALLOWANCE.......................................... 6-23 " G.12.2 PROTLC110N PP.0 CRAM.................................. 6 24 6.12.3 REV0 CATION.......................................... 6-26 6.13 HIGH RADIATION ARFA................................... 6-26 Amendment No. 46 AIE.EE-RO'!E XV Y

/ INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION As a minimum, the fire detection instrumentation for each fire 3.3.3.4 detection zone shown in Table 3.3.6 shall be OPERABLE. Whenever equipment in that fire detection zone is required APPLI C ABILITY: to be OPERABLE. ACT10fi: With the number of OPERABLE fire detection instruments less than required by Table 3.3.6: Within 1 Sour establish a fire watch patrol to inspect the a. zone (s) witu the inoperable instrument (s) at least once per hour, and Restore the inoperable instrument (s) to OPERABLE status within b. 14 days or, in lieu of any other report required by Specification 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.6 within the next 30 days out-lining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status, The provisions of Specifications 3.0.3 and 3.0.4 are not c. a pplica bl e. SURVEILLANCE REQUIREMENTS Each of the above required fire detection instruments snall be 4.3.3.4 demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. m. Amendment No. 46 3/4 3-27 YANKEE-ROWE

( TABLE 3.3.6 FIRE DETECTION If?STRUME!?TS It!STRUMEllT LOCAT10!1 tilillMUM IllSTRUMEliTS OPERABLE 1. Control Room 5 2. Cable Spreading Cable Tray llouse 2 P.anhole I;o. 3 1 3. Switchgear Room 9 4. Diesel Generators 14 0. I 1 tio. 2 1 tio. 3 1 5. Safety Injection Pumps and !!o. 3 Battery 2 Anendment !{Q, 46 YA?;l:E L-RO:'~ 3/4 3 23

4 [ PLANT SYSTEMS 3/4.7.10 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.10.1 The f!rc supp ession water system shall be OPERABLE with; a. Two high pressure pumps, each with a capacity of 1000 gpm, with their discharge aligned to the fire suppression header, and b. An OPERABLE flow path capable of taking suction from the Sherman Pond and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves. APPLICABILITY : At all times. ACTION: a. With one pump inoperable, restore the inoperable pump to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.6 within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system. The provisions of Specifications 3.0.3 and 3.0.4 are not a pplic a bl e. b. With the fire suppression water system otherwise inoperable: 1. Establish a backup fire suppression water system within 24 hours, and 2. Submit a Special Report in accordance with Specification 6.9.6; a) By telephone within 24 hours, b) Confirmed by telegraph, mailgram or facsimile trans-mission no later than the first working day follow-ing the event, and (ANEEE-ROWE 3/4 7-31 Amendment No. 46

( PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) c) In writing within 14 days following the event, out-lining the action taken, the cause of the inopera-bility and the plans and schedule for restoring the system to OPERABLE status. SURVEILLANCE REQUIREMENTS 4.7.10.1 The fire suppression water system shall be demonstrated OPERABLE: a. At least once per 31 days on a STAGGERED TEST BASIS by start-ing each pump. b. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position. c. At least once per 6 months by performance of a system flush. d. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its operating sequence, and: 1. Verifying that each automatic valve in the flow path actuates to its correct position, 2. Verifying that each pump develops at least 1000 spm at a system head of 125 psig, 3. Verifying that each high pressure pump starts to maintain the fire suppression water system pressure > 85 psig. e. At least once per 3 years by performing a flow test of the syster in accordance with Chapter 5, Section 11 of the Fire prciection Handbook,14th Edition, published by the National Fire Protection Association. Amendment NQ. 46 YANKEE-ROWE 3/4 7-32

PLANT SYSTEMS SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.7.10.2 The Cable Tray House spray system shall be OPERABLE. APPLICABILITY: Whenever equipiaent in the spray protected area is required to be OPERABIE. ACTION: With the above required spray system inoperable, establish a a. continuous fire watch with backup fire suppression equipment for the unprotected area within i hour; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.6 within the next 30 days outlining the action taken, the cause of the inoperability and the olans and schedule for restoring the system to OPERABLE status, b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.7.10.2 The above required spray system shall be demonstrated OPERABLE: At least once per 12 months by cycling each testable valve in a. the flow path through at least one complete cycle of full t ravel, b. At least once per 18 months by: 1. Cycling each valve in the flow path that is not testable during plant operation through at least i > complete cycle of full travel. 2. Inspection of the spray needers to verify their integrity, and 3. By inspection of each nozzle to verify no blockage. At least once per 3 years by performing an air flow test c. through each open head spray / sprinkler header and verifying each open head spray / sprinkler nozzle is unobstructed. YANKEE-RDWE 3/4 7-33 Amendment No. 46

PLANT SYSTEMS HIGH PRESSURE C0 SYSTEM 3 LIMITING CONDITION FOR OPERATION 3.7.10.3 The high pressure CO, system located in Manhole No. 3 shall be OPERABLE with at least 90% of full charge weight in the main and auxiliary CO cylinders. 2 APPLICABILITY: Whenever equipment in the high pressure CO2 protected area is required to be OPERABLE. ACTION: a. With the above required high pressure C0 system inoperable, establish a continuous fire watch with b!ckup fire suppression equipment for the unprotected area within 1 hour; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.6 within the next 30 days outlining the action taken, the cause of the inoperability and the plar.s and schedule for restoring the system to OPEPABLE status, b. The provisions of Specifications 3.0.3 and 3.0.4 are not a pplicable. SURVEILLANCE _Pj0VIREMENTS

  • 7.10.3 The above required high pressure C0 systems shall be demon-2 strated OPEPABLE:

a. At least once per 6 months by verifying C0 cylinder weight. 2 b. At least once per 18 months by: 1. Verifying the system valves actuate manually. 2. Performance of a flow test through headers and nozzles to assure no blockage. e mn No. 6 fANKEE-ROWE 3/4 7-34

PLANT SYSTEMS FIRE HOSE STATIONS e LIMITING CONDITIONS FOR OPERATION 3.7.10.4 The following fire hose stations shall be OPERABLE: a. Outside of control room northwest door, and b. Outside of control room northeast door. j APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE. ACTION: a. With one or more of the above required fire hose stations inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) ' rom an OPERABLE hose station within I hour. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.7.10.4 Each of the above required fire hose stations shall be demonstrated OPERABLE: a. At least once per 31 days by visual inspection of the station to assure all required equipment is et the station. o. At least once per IB months by: 1. Pemoving the hose for inspection and re-racking, and 2. Replacement of all degraded gaskets in e aplings. c. At least once per 3 years by: 1. Partially cpening each hose station valve to verify valve OPERABILITY and no flow blockage. 2. Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure available at that hose station. Amendment No. 46 YANKEE-ROWE 3/4 7-35 f-

// l en i.'. PLANT SYSTEMS 3/4.7.11 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION 3.7.11 All penetration fire barriers protecting safety related areas shall be functional. APPLICABILITY: At all times. ACTION: a. With one or more of the above required penetration fire barriers non-functional, establish a continuous fire watch on at least one side of the affected penetration within 1 hour. t. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.7.11 Each of the above required penetration fire barriers shall be verified to be functional by a visual inspection; a. At least once per 18 months, and b. Prior to declaring a penetration fire barrier functional following repairs or maintenance. YANKEE-ROWE 3/4 7-36 Amendment No. 46

3/4.3 INSTRUMENTATION s .D. ASES 3/4.a.1 and 3/4.3.2 REACTOR PROTECTIVE SYSTEM (RPS) AND ENGINEERED SAFEGUARDS SYSTEM (ESS) INSTRUMENTATION The OPEPABILITY of the RPS and ESS instrumentation systems and permissive circuits ensure that 1) the associated ESS action and/or RPS trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained, and 4) sufficient system functional capability is available for RpS and ESS purposes from diverse parameters. The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility g esign for the protection and mitigation of accident and transierit

d...irditions. ILc integrated operaticn of each of these systems is

< ten'istcr.t trith the z sstu.?tions ust d in tha cccir:ent analysts. The serveillance rumie m?ats ver.ified isc these systu;s ca: ) " : t h: oven 11 sys. a fv c.i"r.1 c: ybility it. m ir.teined c: c airi

11.. orip ni c'cir.i s h :Ards.

T'; is. iojic rt: veillanci m'.4 - 't. .To ned et tne minin.:1 f r.:qenci..s a c set ib i;nt to drc.saru F i-1: ',il l t v. t ;e s e - 1 ;i-g es p g. . _.1 wne m.m: - ' wrah

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TL OFi:T ' '" i iY c T the r J.it ' i:. -" i'.e i;r h tre ccati all' :. :::i !! 1 ) M e v.' b r.i n n c: 4-ccu n. %) th.1: n, j j iti::tcd t.i.an ;he ra6id i.:. itsel trip sat;.=in, is a:cceueo. .2 i-ti / : ai cr. ;. ., e. : YANKEE-R0i!E B 3/4 3-1 Amendment No. 46

I I!GTRUMENTATION BASES 3/4.3.3.2 INCORE DETECTION SYSTEM The OPERABILITY of the incore detection system with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the reactor core power distribution. The OPERABILITY of the neutron detectors is demonstrated prior to use by irradiating each detector to be used and normalizing their outputs. 3/4.3.3.3 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This cipebility is required to evaluate the need for initiating (protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "0nsite Meteorological Pro-grams"). 3 /4. 3. 3.4 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the poten-tial for damage to safety related equipment and is an integral element in the overall facility fire protection program. In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection carr.bility until the inoperable instrumentation is restored to OPERABILITY. YANKEE-ROWE B 3/4 3-2 Amendnent No. 46

PLAffT STYSTEMS BASES (Continued) The inspection frequency is based upon maintaining a constant level of hydraulic snubber protection. Thus the required inspection interval varies inversely with the observed snubber failures. The number of inop-erable snubbers found during a required inspection determines the time interval for the next required inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspection per-formed before the original required time interval has elapsed (nonal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval vill I. over ride the previcus schedule. Experience at operating facilities lias shown ti.at the required surveillance program R.;uld assure an acceptable level of snubber performance provided that the seal materials are compatible with the operating cnvironment. !!ydraulic snuM>2rs containing seal raterial which has not F :a . c'emstrat ed by ot era ting ct :.crience, lat or.J cry i-M c e ' t.nalp. : to N comsti'cle with the Ors.Stig ennronrm. Mala N i; i cc.e6 m.. n lii; u cc.d h. g. : c..ic.tif (e. ry 31 6 23 ) .itil :..at;ricl fi. is ccm.?isted. ,,ir cpprcpriate cMn; : si f x.,: vite. tion of dc f o r.c i e t.;ertulic ne' ' r <.'.cr '.1 Ilud m i-r ial.uis t T D : r > at weral IM . L n es b t, s!.1:n C t i-s,. ~ i, s. m. l n t~.. o 1.-- r 3,. n i1 l' i.,

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,t .. c m, tha n.ost ! everc conditions expec ed in l ac.or i.ctallatieas. To further increase the assurance of hydraulic snubber relichility, functional tests should be performed at leaf.t once per 18 months. Dese tests will includc stroking of th hydraulic snf%rs to v:ri:y proper piston movement, lock-up and blet d. Ten percent or ten byt ulic snubbers, whichever is less, represents an adequate sar.ple for sucii tests. Observed failures on these samples should require testing of additional units. Those hydraulic snubbers designrted in Table 3.7.4 as being in high radiation creas or especially difficult to remove need not be selectcd for functional tests provided OPERhBILITY ucs previously verified. Hydraulic sr.ubNrs of rated capacity greater thsn 50,033 lb. cre exempt frem the functional testing requirements because of ti.e inpractichtiity of testing such large units. YAta:EE-ROL'E B 3/4 7-7 Amendment No. 46

4 P BASES 5 3/4.7.10 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occuring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO, Halon and fire hose stations. The collec-2 tive capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program. In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment -E is restored to service. In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Com.ission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant. 3/4.7.11 PENETPATION FIRE BARRIERS The functional int 9rity of the pentration fire barriers ensures that fires will be confir.ed or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving serveral areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passibe element in the facility fire protection program and are subject to periodic inspections. During periods of time when the barriers are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status. YANKEE-ROWE B 3/4 7-8 Amendment No. 46

6.0 ADMINISTRATIVE CONTROLS Administrative controls are the written rules, orders, instructions, procedures, policies, practices, and the de:'gnation of authorities and respond bilities by the management to obtain assurance or safety and quality of operation and maintenance of a nuclear power reactor. These controis shall be adhered to. 6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence. 6.1.2 In all matters relating to the operation of the plant and to. these Technical Specifications, the Plant Superintendent shall report to end be directly responsible to the !% nager of Operations in the Yci. hee t.tomic Electric Company. G.2 OnCA::12/. TIC:! I Cuff.?TE i' fi !s.?.1 The offeite organi?ntien f or fr.cility mar,is.unt and itchn._al .. port shall b: at she 3:a Ficu e 0.7-i. l' !! r m ny m 6.r.1 T!.e Ftcilit; ciga.i.stien sha'.i ir; :.- s!.a.. en figure 6.P M E cc!: i a at, hi r. sh:.ll L. cr g d ni t 4 least t!e ior shif t crew cc.rposition sho.in in lable 6.2-1 b. At least one licensed Operatcr shall be in the control rcom when fuel is in the reactor. c. At least two licensed Operators shall be present in the control room during reactor start-up, scheculed reactor shutdown and during recovery from reactor trips. d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. Operating crew per sonnel trained in radiation protection procedures fill th.s requirement. Y AEE E-R0vlE 6-1 Amendment No. 46 ,4

6.0 ADMINISTRATIVE CONTROLS (Continued) e. Al' CORE ALTERATIONS af ter the initial fuel loading shall be Jirectly supervised by either a licensed Senior Reactor operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. f. A fire brigade of at least 3 nembers shall be maintained onsite at all times. The fire brigade shall not include the minimum shift crew necessary for safe shutdown of the plant, 2 members, or an" personnel reouires for other essential functions during a fire emergency. YANKEE-ROWE 6-2 Amendment No. 46

i E. ~ _. _.cnn l; / ,.e g'. 9 i s ~ 3s a'~ r*1 ? O 9 yy x o ..g 7; tst ? w. Tm, T ier-- w ~ vte. 3 ~ frostArat \\ ~ Vfee - e I Pgeg(Jemt g r _ I.- _, ~., [ ATO l , A'9193*" ho gejQ7 tit" P t "* f ^m t l Trea,.rer

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.= m8 X rn M e 'T7 OEm Pl.nt l (5=re r t n t end ee.;4 l 1 ~ Amsfetent fQCA } Plant [C ry .S_u.pe.r.in. t ende.n t.- y I ____ l i Anfeln f at r.it I ve % In t enanc e 4crat tres d evint leet ttweent & { llealth Phyelce Tc hnten! Chestetty & m Se.=ra to t ger 5urevviant Supervient , ' ev te.*r l [ Step.rvisor Plant seert. Su; Controle he ls tant to the h [ '"3 g Sierc r v ivo r i j l I t i IAssletant l U *tI""9 P

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'J 'a. TABLE 6.2-1 ~ HINIMUM SHIFT CREW COMPOSITION # LICENSE APPLICABLE liDDES - ~h 6 CATEGORY 1, 2, 3 & 4 S 1 50L 1 1* OL 2 1 Non-Licensed 2** 1

  • Does not include the licensed Senior Reactor Operator or Senior P.cactor Operatcr Limited to Fuel litndiing, supervising Core Ali[FDiTIONS af ter the initial fuel Tri./ 'i:.g.
    • 0.+ cc'ditioral nc.n-licent.:d riocrater is reca' ired for IDDE 2 e>. cept

'.to r e ta r titi';.tii hin fo:ir h'>ei o, a s'iu tdorni for u!.it'i tl:e ct.u..t rar, bcui cict rly i s'ablic'r d. t3bifi creii co'.acsi tion ny la br:; ti. :r. Uw 1,n !:m a r' r:>ir, wn.' for ri prried M tuo nM to e>.ce'.:i E V: '. i:: ort e r ' '.) c:ce t-rr d I b nc.' c. Jt '. " C- .. c : 'i. :; . Uc i " 211 i O ref. (-) C b' .I $.. .I L 'I e.1 I l' 'e ' : t: '.. a<.t I s'.s i"".'.1 re f,U i l't ... I', c 1 ithic b.2' l. Y AN KE E-R0i.'E 6-5 ,ec)endraent No. 46

i A_DMINISTRATIVE CONTROLS 6.3 F ACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff listed below shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. a. Plart %perintendent }, b. Assistant Plant Superintendnet Chemistry and liealth Physics Supervisor c. d. Operations Supervisor e. Reactor Engineer f. Maintenance Supervisor g. Instrument and Controls Supervisors h. Shift Supervisors i. Plant ifealth Physicist 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under th Jirection of the Training Coordinctor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Pcrt 55. 6.4.2

  • training program for the Fire Brigade shall be maintained-under the direction of a member of the plant staff appointed to perfor:

the duties of Fire Protection Coordinator and shall meet or exceed the requiremnts of Section 27 of the NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly. [35 REVIEW AND AUDIT 6.5.1 PLANT OPERATION REVIEW COMMITTEE FUNCTION 6. 5.1.1 The Plant Operation Review Comittee (FORC) shall function to advise the Plant Superintendent on all matters related to nuclecr scfety. Y/SnEL-ROWE 6-6 Amendment No 46

4 ADM1HISTRATIVE CONTROLS C0!iPOSITION 6.5.1.2 The Plant Operation Review Committee shall be composed of the: Chainnan: Plant Superintendent Vice Chairman: Assistant Plant Superintendent Member: Operations Supervisor Member: Maintenance Supervisor Member: Reactor Engineer Member: Chemistry and Health Physics Supervisor Member: Instrument and Control Supervisor Membcr: Plant Health Physicist ALTERNATES 6.5.1.3 All alternate menbers shall ce appointed in writing by tho PORC Chairmen to erve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities cr count tuxard a PORC quorum at any one time. MEETl!.3 FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or Vice Chairman. QUDRU!' 6.5.1.5 A quorum of the PORC shall consist of a minimum of five people as follows: a. The Chairman or Vice Chairman plus four members, or b. The Chairman and Vice Chairman plus three members. RESPONSIBILITIES 6.5.1.6 The Plant Operation Review Committee shall be responsible for-Review of 1) all procedures required by Specification 6.8 a. and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Superintendent to affect nuclear safety. Y AN K E E -RO',lE 6-7 Amendment No. 46

ADMINISTRATIVE CONTROLS b. Review of all proposed tests and experiments that affect nuclear safety. c. Review of all proposed changes to the Technical Specifications. d. Review of all proposed changes or modifications to plant systems or equignent that affect nuclear safety. e. Investigation of all violations of the Technical Specifications including the preparation end forwarding of reports covering evaluation and recomendatic,s to prevent recurrence to the Manager of Operations and to the Chairman of the Nuclear Safety Audit and Review Comittee. f. Review of events requiring 24 hour written notification to the Commission. g. Review of facility operations to detect potential nuclear safety hazards. h. Performance of special reviews, investigations of analyses and reports thereon as requested by the Chaiman of the Nuclear Safety Audit and Review Comittee. i. Review of the Plant Security Plan and implementing procedures and shall srbmit recomended changes to the Security Advisor. j. Review of the Emergency Plan and implementing procedures and shall submit recomended changes to the Radiction Protection Manager. AUTHORITY 6.5.1.7 The Plant Operation Review Comittee shall-a. Reco rnend to the Plant Superintendent, written approval or dis-approval of items considered under 6.5.1.6(a) through (d) above. b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question. c. Provide written notification within 24 hours to the Manager of Operations cf disagreement between the PORC and the Plant Superintendent; howeve.:r, the Plant Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above. lYA!;KEE-ROWE 6-8 Amendment No. 46

ADMINISTRATIVE CONTROLS RECORDS 6.5.1.8 The Plant Operation Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Manager of Operations and Chairman of the Nuclear Safety Audit and Review Committee. 6.5.2 NUCLEAR SAFETY AUDIT AND REVIEk COMMITTEE FUNCTION 6.5.2.1 The Nuclear Safety Audit and Review (NSAR) Committee shall functinn to provide independent review and audit of all aspects of plant safety. Adequacy of this review and audit is assured by the cross sec-tion of disciplines required of the Committee membership as described in Section 6.5.2.3. COMPOSITION 6.5.2.2 The NSAR Committs-shall be composed of at least six persons with the Committee membership and its Chairman and Vice Chairman appointed by the Yankee Atomic Electric Company Vice President or such person as he shall designate, a. Chairman b. Vice Chairman Four technically qualified persons who are not members of the c. plant staff. QUALIFICATION 6.5.2.3 Membership to the NSAR Committee requires that an individual meet one of the below academic and/or experience requirements: Bachelor Degree or equivalent, plus five (5; years total a. experience in the below listed disciplines. b. Nine (9) years total experience in the below listed disciplines: (a) Nuclear Power Plant Technology (b) Reactor Operations (c) Utility Operations (d) Power Plant Design (c) Reactor Engineering (f) Radiation Safety YANKEE-ROWE 6-9

@endment No. 46

ADMittlSTRATIVE CONTROLS i (g) Safety Analysis (h) Instrumentation and Control (i) Metallurgy (j) Quality Assurar.e ALTERilATES 6.5.2.4 All NSAR Committee alternate members shall be apppointed in writir.g by the Yankee Atomic Electric Company Vice President, or such person as he may designate, to serve on a temporary basis; however, no more than two alternates shall participate as voting members in IThR Ccmmittet activities at any one time. L C.",'JLTA"TS

6. r,. 2. 5 Cr.nr.iriter.ts rny be utiliz-d as daten.im. d iy the !.9.ii Q Y,-

( u .n to provids expert advice, tdwr. ncr:Od, to U:e H5'? L:ai. l ,..E_T !_. . _I.F U. i'J._r_!_.C__' !^ E.5 1:- " '" ^ -- ii .c si 'll 1: 't t 1-rn si:: I .V

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lli ne ci t... Chriier:,b by toa Vic .v eg,, I! l (.. I i 6.5.E.7 A f$f.7 Cur r.iitte quorrm shell consist of I cinia a r! fie me.bers as follows: a. The Chairman or Vice Chairman plus four members (or two me;r.bers plus two alternates). b. The Chairman and Vice Chairman plus three tcmbers ( or one member plus two alternates). c. Those versennel from the organizztion reporting to the Manager of Operations shall always be in the minority. WiKE E-RO'n'E 6-10 Amendment No. 46

"i 4 ADMINISTRATIVE CONTROLS REVIEW 6.5.2.8 The NSI.R Conuittee shall review: a. The safety evaluations for 1) changes to equipment er systems and 2) tests or experiments completed under the pro-visions of Section 50.59, 10 CFR, to verify that such actiLas did not constitute an unreviewed safety question. b. Proposed changes to equipment or systems which involve an unrevic. 2d safety question as defined in Section 50.59, 10 CFF.. c. Proposed test or experiments which involve an unrnvieced safety question as defined in Section 50.!9, 10 CFR. d. Proposed changes to Technical Specifications or this Operating License, c. Violatirm 9f cm'es, rectilatior, ereert. Tcchnical t : -i; e u I ca ti on.., in ns: n.' ':i r. v., o r < ^ W...1 p t c.ce -J (I or iis;: nions havir.g nada.c s t.icty sign icance, f. Sip;;fi: at op?: :th:j abn;4 "i. h s or 6 i;tions fr. !j e nd :, p. c.' 3 N r c.. ' n '. r-ci pl i h. t.i si.f t t,, _cii; d. i. .,iin j. p. Eve nt s t e rrui ri ra ? '.10er - at a,ic;.. ' to ' l' i- .ti., h;n a ' n. g - i-. ir rt );;c e ,i, ei.., , r. - :, .i 4 ,t .t ; ! ;, 1 tho o r,. 'I (; ,s... i ti i.! Oil 5 0.5.2.9 Audits of facility activities shall be p?rfcrr.ed under the cognizcnce of the HSI.R Comittee. Tl'ese cudi ts shall enrupw s: a. The confcrmance of f acility operation to provisions contained within the Technical Specifica' ions and applicable license conditicus at least once per ' 2 renths, + 25%. YANKEE-ROME 6-11 Amendment No. 46

ADMINISTRATIVE CONTROLS b. The performance, training and qualification of those mt :bers of the facility staff who have a direct relationship to operation, maintenance or technical aspects of the plant, at least once per 12 months, i 25%. c. The results of actions taken to correct deficiencies occur-ring in facility equipment, structures, systems or method of operosion that affect nuclear safety at least once per 6 months, 1 25%. d. The perfomance of activities required by the Operational Quality Assurance Program to meet the criteria of Apperdix "B", 10 CFR 50, at least once pre 24 months, i 25%. e. The Facility Emergency Plan and implementing procedures at least once per 24 months, t 25%. f. The Facility Security Plan and implementing procedures at least once per 24 months, i 25%. g. The Facility Fire Protection Program and implementing proce-dures at least once per 24 months, i 25%. h. Any other area of f acility operation considered appropriate by the NSAR Comittee or the Vice President. AUTHORITY 6.5.2.10 The NSAR Comittee shall report to and advise the Vice President on those areas of responsibility specified in Sections 6.5.2.8 and 6.5.2.9. RECORDS 6.5.2.11 Minutes of each NSAR Comittee meeting shall be prepared and forwarded to the Vice President and each member of the Committee for review within 20 working days following each meeting. The meeting minutes shall incluae, where applicable, reports of reviews encompassed by Section 6.5.2.8; and reports of audits encompassed by Section 6.5.2.9. The review of the minutes shall be completed within 60 days of the date of their distribution. 6.5.3 INDEPENDENT AUDIT AND REVIEW 6.5.3.1 An independent fire protection and loss prevention program inspection and audit shall be perfomed at least once per 12 months utilizing either qualified offsite licensee personnel or an onsite fire protection firm. YANKEE-ROWE 6-12 Amendment No. 46

.I ( ' ADMINISTRATIVE _ CONTROLS 6.5.3.2 An inspection and audit of the fire protection and loss pre-vention program shall be performed by a qua'.i'i:d easide fire consultant at least once per 36 months. 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES: The Comission shall be notified and/or a report submitted a. pursuant to the requirements of Specification 6.9. b. Each REPORTABLE OCCURRENCE requiring 24 hour notification to the Comission shall be reviewed by the FORC and sub-mitted to tne NSAR Comittee and the Manager of Operations. 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: The facility shall be placed in at least HOT STANDBY within a. one hour. b. The Safety Limit violation shall be reported to the Comission, the Manager of Operations and to the NSAR Committee within 24 hours. A Safety Limit Violation Report shall be prepared. The c. report shall be reviewed by the Fiant Operation Review Committee. This report shall describe (1) applicable cir-cumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, ar.d (3) corrective action taken to prevent recurrence. d. The Safety Limit Violation Report shall be submitted to the Ccamission, the NSAR Comittee and the Manager of Operations within 14 days of the violation. 6.8 PR3CEDURES 6.8.1 Kritten procedures shall be established, implemented and main-tained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix "A" of Regulatory Guide 1.33, November 1972, except as provided in 6.8.2 and 6.8.3 belcw. The written procedures shall also cover the activities relating to the Fire Protection Program implementation. Y A';KE E-ROWE 6-13 Amendment No. 46

ADMINISTRATIVE CONTROLS 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the Plant Operations Review Committee and approved by the Plant Superintendent prior to implementa-tion and reviewed periodically as set forth in administrative' procedures. 6.8.3 Procedures that have been developed as a result of changes defined in 10 CFR 50.59(a)(2) shall be independently reviewed to verify that the implementing actions do not constitute an unreviewed safety question. Those reviews shall be performed by Nuclear Service Division personnel having qualifications at least equivalent to those specified for NSAR Committee membership in 6.5.2.3. The procedures shall be approved by the Pianager of Operations, NSD. 6.8.4 Temporary changes to procedures of 6.8.1 above may be made provided: a. The intent of the original procedure is not altered. b. The change is approved by two members of the plant management staTf, at least one of whom holds a Senior Reactor Operator's G :ense. c. The change is documented, reviewed by the PORC and approved by the Plant Superintendent within 14 days of implementation. 6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspec-tion and Enforcement unless otherwise noted. The reporting requirements of Specifications 6.9.1, 6.9.2, 6.9.3 and 6.9.4 are in accordance with Revision 4 of Regulatory Guide 1.16. " Reporting of Operating Information - Appendix "A" Technical Specifications." ROUTINE REPORTS 6.9.i Startup Report. A summary report of plant startup cnd power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving and planned increase in power level, (3) installation of fuel that has a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FHSR and shall in general include a description of measured values of the rerating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain sctisfactory operation shall also be described. Any additional specific details required in license conditions based on other connitments shall be included in this report. YANKEE-ROWE 6-14 Amendment No. 46

J ADMllilSTRAil.'E CONTROLS (d) Total dissolved gas radioactivity (in curies) and average concentration released to the unrestricted area. (e) Total volume (in liters) of liquid waste released. (f) Total volume (in liters) of di'.ution water used prior to release from the restricted area. (g) Total gross radioactivity (in curies) by nuclide released based on representative isotopic analyses performed. (h) Percent of Technical Specification limit for total radioactivity. (3) Solid Wastes (a) The total amount of solid waste shipped (in cubic feet). (b) The total estimated radioactivity (.n curies) involved. (c) Disposition including date and destination. 6.9.6 Special renorts shall be submitted to the Director of the Of' ice of inspection tr' Enforcement Regional Office within the tine pericci specified fcr c n1 report. These reports shall be submitted covering the activitics t ;ntified belcw pursuant to the requirements of the applicable refcre ce specifict. tion: a. Irervice Inspection Program Revie'..'s, Specification 4.4.9.1. b. ECC5 1:tuation, Specifications 3.5.2 and 3.5.3. c. a r.c ; tele tieteorological l'.onitoring Instruaent ation, Specifi-cation 3.3.3.3. d. Sealtd Source leakage in excess of limits, Specification 4.7.6.3. e. Radicactive Solid Maste Disposal, Specification 3.7.9.1. -f. Fire D2tection Instrumentation, Specification 3.3.3.4. g. Fire Suppression Systems, Specificatior.s 3.7.10.1, 3.7.10.2 and 3.7.10.3. Y ANin - RD'..T 6-21 Amendment flo. 46

ApMINISTRATIVE CONTROLS 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years: Records and logs of facility operation covering time interval a. at each power level. b. Records and logs of principal maintenance activities, inspection, repair and replacement of principla items of equipment related to nuclear safety. A c. All REPORTABLE OCCURRENCE reports submitted to the COMMISSION. d. Records of surviellance activities, inspections and calibrations required by these Technical Specifications. e. Rect-ds of reactor tests and experiments. f. Records of changes made to Operating Procedures. g. Records of radioactive shipments. h. Records of sealed source leak tests and results. i. Records of annual physical inventory of all sealed source material of record. 6.10.2 The following records shall be retained for the duration of the facility Operating License: Records and drawing changes reflecting facility design modifi-a. cations made to systems and equipment described in the Final P-js Sunnary Report. b. Records of new and irradiated fuel inventory, fuel transfers and as sembly burnup histories. c. Records of facility radiation and contamination surveys. d. Records of radiation exposure for all individuals entering radiation control areas. Records of gaseous and liquid radioactive material released to e. the environs. f. Records of transient or operational cycles for those facility components identified in Table 5.7-1. YANKEE-ROWE 6-22 Amendment No. 46 .}}

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