ML20147D873

Amend 170 to License DPR-35,revising Definition of operable- Operability,Tss & Associated Bases Section for TSs 3.9.B.2 & 3.9.B.3

ML20147D873
Person / Time
Site:	Pilgrim
Issue date:	02/10/1997
From:	Milano P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20147D880	List: ML20147D873 ML20147D882
References
NUDOCS 9702180080
Download: ML20147D873 (15)

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{{#Wiki_filter:__ me.% j. p \\ UNITED STATES l g NUCLEAR REGULATORY COMMISSION i WASHINGTON. D.C. 38054001 l 4 BOSTON EDIS0N CONPANY j DOCKET N0. 50-293 i i l PILGRIN NUCLEAR POWER STATION i { AMENDNENT TO FACILITY OPERATING LICENSE i i I Amendment No.170 i License No. DPR-35 l 1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that: i I A. The application for amendment filed by the Boston Edison Company (the licensee) dated April 25, 1996, as supplemented on December 23, 1996, 4 complies with the standards and requirements of the Atomic Energy Act i of 1954, as amended (the Act), and the Commission's rules and regulations; i B. The facility will operate in conformity with the application, the i provisions of the Act, and the rules and regulations of the Commission; f C. There is reasonable assurance: (i) that the activities authorized by i 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 safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-35 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.170, are hereby incorporated in the license. Tne licensee shall operate the facility in accordance with the Technical Specifications. 9702180000 970210 PDR ADOCK 05000293 p PDR . - ~ _ _ - ~ ~,.

.-_.-~.-. , i 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days. FOR THE NUCLEAR REGULATORY COMISSION Y ^^ Patrick D. Milano, Acting Director Project Directorate I-3 Division of Reactor Projects - I/II office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 10, 1997 l l i i

i ATTACIMENT TO LICENSE AMENDMENT NO.170 l FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications with i the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Remove Insert 1.1 1.1 3/4.4-1 3/4.4-1 3/4.5-7 3/4.5-7 3/4.7-11 3/4.7-11 3/4.7-12 3/4.7-12 3/4.7-13 3/4.7-13 3/4.7-14 3/4.7-14 3/4.7-15 3/4.7-15 3/4.7-16 3/4.7-16 3/4.9-4 3/4.9-4 B3/4.7-10 B3/4.7-10 B3/4.7-12 B3/4.7-12 1 i l l

( l i l 1.0 DEFINITIONS 'Ibe succeedag frequently used terms are explicitly defined so that a unifonn interpretation of the j g m-== may be acineved. j A. Safety. List ) 1he safety limits are limits below which the r=aa=hh h of the cladding and i pnmary systans are assured WW such a limit is cause for unit shutdown and review l by the Nuclear Reguissory Commusion before resumption ofunit operation Operation beyond such a limit may not in itself result in serious y but it indmates an j operational % subject to regulatory renew. l B. Linutag Safety System Sattus (LSSS) l The Imutmg safesy system settings are settings on instru==mewian which initiate the automatic e protective action at a level such that the safety heruts will not be awaadad The region i between the safety limit and these settags represent marge with normal operation lying below these settags The marge has been establinhad so that with proper operation of the i instrumentation the safety limits will never be exceeded. i j C. Limiting Conditions for Operatmn (LCO) 1 f The Imutmg conditions 'for operation specafy the minimum acceptable levels of system l performance necessary to assure safe startup and operation of the facihty. When these i conditens are met, the plant can be operated safely and abnormal situations can be safely controlled i I D. Core Oneratine Limits Reoort j i 1he CORE OPERATING LIMITS REPORT is a reload cycle specific document, its i supplements and revisions, that provides core operating limits for the current operatmg reload j cycle. These cycle specific core operstmg Imuts shall be determined for each reload cycle in mic.cc with Specification 6.9.A.4. Plant operation within these operating limits is addressed in individual specifications E. Onerable - Onerability l A system, subsystem, train, w..ycz.cr. or device shall be OPERABLE or have OPERABILITY when it is capable of performmg its pf-l function (s). Implicit in this defimtion shall be the assumptaon that all necessary attendant instrumentation, controls, l normal or emergency electncal power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its fuMs) are also capable of performmg their related support funciaon(s). F. Ogsabas L l Operatmg means that a system or component is performag its intended functions in its I required manner. i i 11 Amendosatlis.,438,170 i

) LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LlOUlD CONTROL SYSTEM i Soeoficabon:

1. When tested as specified in 3.13 Two SLC subsystems shall be OPERABLE.

verify that each pump delivers at least 39 GPM against a system head of 1275 psig. Acohcability:

2. Manually initiate one of the Standby i

Run and Startup MODES Liquid Control System loops and pump domineralized water into the l reactor vessel every 24 months on a j STAGGERED TEST BASIS. l Operation with inoperable Eauioment

3. Verify continuity of explosive charge every 31 days.

I A. With concentration of boron in solution not

4. Verify available volume of sodium within limits but > 8%, restore concentration pentaborate solution is within the of boron in solution to within limits within 72 limits of Figure 3.4-1 or 2 4000 hours AND 10 days frore discovery of j

failure to meet the LCO. gallons every 24 hours. i B. With one SLC subsystem inoperable for reasons other than Condition A,

5. Verify temperature of sodium i

pentaborate solution is > 48"F every i

1. ensure that the diesel generator 24 hours.

i associated with the operable SLC subsystem is operable;

6. Verify the concentration of boron in solution is s 9.22 % weight and within l

M the limits of Figure 3.4-1 every 31 days; I [

2. restore SLC subsystem to OPERABLE g

status within 7 days M 10 days from } discovery of failure to meet the LCO. Once within 24 hours after water or boron is added to solution; C. With two SLC subsystems inoperable for reasons other than Condition A, restore one M SLC subsystem to OPERABLE status 3 within 8 hours, Once within 24 hours after solution temperature is restored to > 48' F.~ D. Required Action and associated Completion Time not met, be in Hot Shutdown within 12

7. Verify sodium pentaborate enrichment i

hours. is 2 54.5 stom percent B 10 prior to addition to SLC tank. 4 4 8 Verify all heat traced piping between storage tank and pump suction is unblocked every 24 months. M i Once within 24 hours after solution temperature is restored to > 48* F.

9. Verify temperature of pump suction j

piping is > 48'F every 24 hours. h Revision Amendment No. 102, 99,15e,170 Page 3/4.4-1

LIMITING CONDITION FOR OPERAT10N SURVEILLANCE REOUIREMENT l 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING ( SYSTEMS (Cont) SYSTEMS (Cont) i F. Maimum Low Pressure Cochng and Dunel F. Im 7.=e C= '====d D:=' i Genamtor Avadabahty Generator Availabahty l

1. During any penod when one diesel

1. When it is determmed that one diesel generator is inoperable, an=hanad reactor generator is inoperable, wnhin 24 hours, operation is permissible only during the determee that the operable diesel generator succeedag 72 hours unless such diesel is not inoperable due to a common cause generator is sooner made operable, provided

failure, that allc(thelow pressure core and annemianwar coohng systems and the et i

mnaimag cheselgenerator shall be i operable. If this requirement cannot be met, perform survallmane 4.9.A.I.a for the 4 an orderly shutdown shall be intiated and operable diceelgenerator, the reactor shall be placed in the Cold Shutdown Condition wnhm 24 hours. and j

2. Any combination ofinoperable w..r within I bour and once every 8 hours e

in the core and nantamment coohng systems thereafter, venfy correct breaker alignment shall not defeat the capability of the and indicated power availability for each remaimag operable w..yes.a. to fulfill the offsite circuit. coohng functions A When irraduted fuel is in the reactor vessel and the reactor is in the Cold Shutdown ea-d%. both core spray systems, the LPCI and nantamment cooling systems may be inoperable, provided no work is bemg done which has the pawi=1 for draimag the reactor vessel.

4. Dming a refuehng outage, for a period of 30 days, refueling operation may continue provided that one core spray system or the LPCI system is operable or Specification 3.5.F.5 is met.

Amendesa No. If, Tff,170 3/4.5-7

~ LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 1 1 3.7 COlRAINMENT SYSTEMS (Cont.) 4.7 CONTAINME!R SYSTEMS (Cont.) f i l A. Primary Centainning (Cont.) l With no H2 analyser operable, mactor j operation is allowed for up to 48 hours. j Ifone of the inoperable analysers is not madeibily operable within 48 hours, i the nector shallbein a least Hot l Shutdown wittun the next 12 hours B. Standbv Gas Treatment Svstern and Control B. Standby Gas Trenament Syslam and Commi j Roarn High Efficiency Air Fdtratmn Svstan Room Hmh EfEcaency Air Filtration Svnen l

1. Standby Gas Treatment System 1.

Stan6y Gas TW System i

a. Except as specified in 3.7.B.I.c or a.

1. At least once per operating cycle, 3.7.B.I.e below, both trains of the it shall be damanserated that i

standby gas treatment system shall be pressure drop across the combined operable when in the Run, Startup, high *W filters and charcoal i and Hot Shutdown MODES, during adsorber banks is less than 8 l movement ofirradiated fuel inches ofwater at 4000 cfm. assemblies in the earnadary cantainment, and durmg movement of

2. Atleast anoe per operatag cycle, j

new fuel over the spent fuel pool, and demonstrate that the inlet besters j during CORE ALTERATIONS, and on each train are operable and are i during operations with a potential for capable of an output of at least 14 i draining the reactor vessel kW. (OPDRVs),

3. The tests and analysis of g

Specification 3.7.B.I.b. shall be performed at hast once per 1 the reactor shall be in cold shutdown operating cycle or following withm the next 36 hours. pastag, fire or charmcal release in any v=hle sone b.

1. The results of the in-place cold communicating with the systan

{ DOP tests on HEPA filters shall 3lgitthe system is operatag that i showit99% DOP removal. The could contaminate the HEPA l results of hala:aaH filters or charcoal adsorbers hydrocarbon tests on charcoal adsorber banks shall showit99%

4. At least once per operatag halogenated by&ds cycle, automatic intiation of I

removal. t l l l t Ii 1 i l Amendment No. :,'2, 00,!!, 50, !!:, " ", !!!,!::,170 3;4.7 11

a e j MMITING CONDITIONS FOR OPERATION $URVEILLANCE REOUIREMENTS } 3.7 CONTAINMENT SYSTINS (Cont.) 4.7 COfRAINMENT SYSTEMS (Cont.) i B. Stanew Gas Tmatment Svstem and Cantml B. Standw Gas Treatment Svmese and Casaral j Raam High Efficaanev Aar Fdtration Svntam Raam High EfBcasacy Air Fderation Svearn j (Cont.) (Cont.) j

2. The results of the laboratory carbon endt branch of the stan&y gas sample analysis shaR show 295%

tr==rmanr system shallbe methyliodide removalat a velocity demaaserated, with within 10% of systen design,0.5 to 1.5 Specification 3.7.B.I.d nis/m3 inlet methyliodide

==ri=Aad j concentration,270% R.H. and 2190*F. i The analysis results are to be venfied as 5. Each train ofthe standby gas acceptable within 31 days after sample treatment systen shallbe removal, or declare that train inoperable operated for atleast 15 nunutes and take the actions specified in per month 3.7.B.I.c. l 6. 'Ihe tests and analysis of j

c. Finm and after the date that one train of the SynAce= 3.7.B.1.b.2 shall l

Standby Gas Treatment System is made or be i fow.d after every 720 j found to be inoperable for any reason, hours ofsystem operation j contmuod reactor operation, irradated fuel l handhng,'or new fuel handhng over the b. 1. In-place cold DOP testag shall l spent fuel pool is perimssible only during be i fva.d on the HEPA the mW sevat days providingthat filters after each completed or t within 2 hours all active wg-:== of the partial replacement ofthe other standby gas treatmmt train are HEPA filter bank and after any verified to be operable and the diesel structural maintenance on the I generator==ae!M with the operable train HEPA filter system housing l is operable. which could affect the HEPA 1 filter bank bypass leakage l If the system is not made fully operable l within 7 days, reactor shutdown shall be 2. Halogenated hydrocarbon i istiated and the reactor shall be in cold testag shallbe performed on i shutdown withm the next 36 hours and fuel the charcoal adsorber bank after kaadline operations shall be termmated each partial or complete within 2 hours. replacemmt of the charcoal } adsorber bank or after any i Fuel handhng operations in progress may structural maineaaaace on the be completed. charcoal adsorber housing which could affect the charcoal li adsorber bank bypass leakage i, l 1 i i i { l i hasedmont No.'2,"",51,1?2. it, t"t,170 3M.712 I

- 3 . -. - -... -.~. a l LBETING CONDITIONS FOR OPERATION SURVEILLANCEREOUIREMENH l 3.7 CONTAINMENT SYSMMS (Cont.) 4.7 CONTAINMENT SYSTEMS (Cont.) i B. Stanew Gas Treatment System and Control B. Stanew Gas Trentant Svstam and Contml j Room Egh EfEcasacy Air Fdtratan System Room Egh Ef5cumev Air Fdtraban System i (Cont.) (Cont.) i d. Fans ahnIIoperate vnshin

• 10% of f

4000 cib. J 4 e. From and aAer the date that one train of the Standby Gas Treatment System i is made or fbund to beinoperable for j any reason during Refuel Outages, i --- ?---{-5 operations are permissible l caly during the sucomeding 7 days j providing that withm 2 hours all active componnats of the other train l are venfied to be operable and the i du.el senerator==-a*M with the operable train is operable. l 1 If the systesn is not made fully i l operable withm 7 days, i } i) place the operable trainin j operation immediately E i j ii) suspend movement ofirradiated i fue! assemblics in Wa y j canemin.nent or new fuel h= aria: over the spent fuel pool or core. i Any fuel assembly movement in progress i may be completed. i 1 4 i e i I+ s 4 3 Amendment lie. '. *^. 51. "2.101 ? t, ?14.151, t e!,170 3g.713 i ? 1

LIMrI1NG CONDITIONS FOR OPERATyry SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont.) 4.7 CONTAINMENT SYSTEMS (Cent.) { B. Statuv Gas Treatment Svann and Camami B. Stanerv Gas Tmatment Svstem and Consmi i Raam Egh Effumancy Air Filtration Svenn Rone Egh EfBcasacy Air Filtration System (Cont.) (Cont.) i

2. Cantml Raam High EfEcianev Air

2. Camrni Room Mah EfEciency Air j

Filtration Svsten Faltataan hainn

a. Except as speci6ed in Spacineneian

a. At least once per operatag cycle the 3.7.B.2.c or 3.7.B.2.s below, both pressure drop across each combined trains of the Control Room High Sker train shall be demonstrated to be j

RW Air Fikration System used for less than 6 inches ofwater at 1000 l the processeg ofinlet air to the control cfm or the cale=Intad equivalent. room under accident condmons shall be operable when in the Run, Startup, and Hot Shutdown MODES,during movement ofirradiated fuel assemblics in the mannadary containment, and

b. 1. 1he tests and analysis of during movement ofnew fuelover the Specification 3.7.B.2.b shall be spent fuel pool, and during CORE WL.. d once per operating ALTERATIONS, and during operations cycle or following pamtag,6:e with a potential for draming the reactor or chemical release in any vessel (OPDRVs),

vanhinhan zone =--- ~ - = --; with the system while the a systemis operatmg the resctor shallbe in cold shutdown within the next 36 hours.

2. In place cold DOP testag shallbe performed aAer each complete or partial replacement of the HEPA Siter bank or aAer any structural b.

1. The resuhs of the in-place cold maintenance on the system DOP tests on HEPA filters shall housing wiuch could affect the show 299% DOP removal lhe HEPA filter bank bypass leakage results of the halogenated hydrocarbon tests on charcoal

3. Halogenated hydrocarbon testing adsorber banks shall show 299%

shallbe performed aAer each hak =rd hyiweites removal complete or partial replacement when test resuhs are extrapolated of the charcoal adsorber bank or to the imtsation of the test. aAer any structural ma=taamme on the system housing which 2. The results of the laboratory carbon could affect the charcoal adsorber angle analysis shall show 295% bank bypass leakage methyliodide removal at a velocity wnhin 10% ofsystem design,0.05

4. Each train shall be operated with to 0.15 mg/m3 inlet methyliodide the heaters in automatic for at eaan-eration, 270% R.H., and least 13 minutes every month.

2125'F. The analysis resuhs are to be veri 6ed as acceptable within 31 days aner sample removal,or declare that train 5 tic and take the actions specified in 3.7.B.2.c. Amendment No. '2, "". "2, ? ? 2, ? ". t'!, tat,170 314.7 14 i

LIMITING CONDITIONS FOR OPERAT10N $URVEILLANCEBEOUIREMENTS i i 3.7 CONTAINMENT SYSTEMS (Cont.) 4.7 CONTAINMENT SYS1 EMS (Cont.) B. Standbv Gas Tnument Svsten and Control B. Standiv Gas Tamament Symam and Control 4 i Room Hagh EfEconcy Air Filtraten System Rann High EfEcumev Air Filtra:mn Svsten l (Cont.) (Cas.) j

5. 'Ilie test and analysis of l

W 3.7.B.2.b.2 shall be performed aAer every 720 l bours ofsystem operation. i j

c. From and aAer the date that one train of c.

Atleast once per operating cycle j the Control Room High R% Air demonstrate that the inlet heaters Filtration Systen is made or found to be on each train are operable and inoperable for any reason, reactor onpable of an output of atleast 14 operation, arradiated fuel handling, or kw. j new fuel bandhas over the spat fuel i . Poolis permissible only during the =wh g 7 days providag that withm j i j 2 hours all active components of the d. Perform an instnament functianal ether CRHEAF train are venfied to be test on the hunndistats controlhng } operable and the dieselgenerator the heaters once per operatag i masarintal with the operable train is cycle. j operable. If the system is not made j i fully operable within 7 days, reactor i shutdown shallbeistaated and the i reactor shall be in cold shutdown within f g the next 36 hours and fuelhandhng operations shall be termmated within 2 hours. Fuel 6~he operations in progres: maybecompleted.

d. Fans shall operate within

• 10% of 1000 cfm.

l

e. From and aAer the date that one train of the Control Room High 56% Air Fikration Systemis made or found to be inoperable for any reason during Refuel Outages, refuehng ope.h are permissible only duringthe sum 47 days providing that withm 2 hours all active components of the other train are venfied to be operable and the diesel sacrator ameariatai with the operable trainis operable.

If the system is not made fully operable wahm 7 days, Amendment No. '.2,"",5!,57, ? ?2 ?ti, !5!,?^?,170 314.7 15

._.__7 i blMIT1NG CONDITIONS FOR OPERAT10N $TRVEILLANCE REOUIREMENTS i l 3.7 CONTAINMENTSYS1 EMS (Cont.) d.7 CONTAINMENT SYS'IEMS (Cont.) i) perform survedlance 4.7.B.2.b.4 for the operabic CRHEAF every 24 hours i E i ii) suspend novament ofirradiated fuel j assemblies in annandary aantainaww ] er new fuel handhng over the spent 3 feel pool or core. l Any fuel assembly movement in progress may l be completed. l C. Sennadary Cantainment C. Secondary Cantamment l

1. henadary nanemia-aar shall be OPERABLE

1. Each idA outage prior to i

when in the Run, Startup and Hot Shutdown .er" ;. maaandary containment MODES, during movement ofirradated fuel capability shallbe denonstrated to l assemblies in the aamadary aantamment, and mamtain 1/4 inch ofwater vacuum hring movement of new fuel over the spent fuel under calm wind (5 mph) condit ons j pool, and during CORE ALTERATIONS, and with a filter train flow rate ofnot j during operations with a y-*M for draining more than 4000 cfm. i the reactor vessel (OPDRVs). i l

2. a. With Samadary Containment inoperable when in the Run, Startup and Hot Shutdown i

l MODES, restore Sacandary Containment to l OPERABLE status within 4 hours. l i

b. Required Action and Completion Time of 2.a not met,be in Hot Shutdown in 12 hours j

M Cold Shutdown withm 36 hours.

c. With hmadary Contamment inoperable during movement ofirradated fuel j

assemblies in the aacaadary caatainment, and j during movement of new fuel over the spent l fuel pool, and durmg CORE l ALTERAT10NS,and during OPDRVs, immodately l

1. Suspend movement ofirradated fuel assemblies in the aamadary containment i

M

2. Suspend movement of new fuel over the j

spent fuel pool. - M i

3. Suspend CORE ALTERATIONS.

) M ~ j

4. Inmate acten to suspend OPDRVs.

1 i Assedmont Ns.". !*t, ?"",170 3M.718 4 i

EIMITING CONDITION FOR OPERATION $URVEILLANCE REOUIREMENTS I 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM (Cont) (Cag) } B. Operation vnth Inoperable Equipment A. Auxaharv Electncal Equipment Surveillance ICGD0 Whenever the reactor is in Run Mode or i Startup Mode with the reactor not in a Cold

3. Emergency 4160V Buses A5-A6 l

Cd% the availabihty ofelectne power Degraded Vokage Aanuaantum shall be as spec Sed in 3.9.B.1, 3.9.B.2, System. 3.9.B.3, 3.9.B.4, and 3.9.B.5.

a. Once each operatmg cycle, i

1. From and aAer the date that incoming power calibrate the alarm sensor l

is not available from the startup or shutdown transformer, cant==d reactor w.I;ce is

b. Once each 31 days perform a 4

l pernussible under this condition for seven ehmanal functionaltest on the days. During this penod, both diesel alarm systan i generators and===~iatM emergency buses l g must remam operable. c. In the event the alarm system is detenmned inoperable under 3.b 3

2. From and aAer the date that incommg power above, commence loggmg is not available from both startup and safety related bus voltage every i

shutdown transformers, anat=ied operation 30 minutes until such time as l is permissible, provided both diesel the alarmis restored to operable generators and===~imed emergency buses status. [ remain operable, all core and caatmiament i cooling systems are Operable, reactor power

4. RPS Electrical Protection Assemblies level is reduced to 25% of design and the NRC is noti 6ed within one(1) hour as a.

Each pair of redundant RPS required by 10CFR50.72. EPAs shall be detenmned to be i operable at least once per 6 i

3. From and aRer the date that one of the diesel months by performance of an generators or associated emergency bus is instrument fwiaani test.

made or found to be inoperable for any reason, coutinued reactor operation is

b. Once per 18 months each pair I

permissible in asideixe with Specifications of redundant RPS EPAs shall i 3.4.B.1, 3.5.F.1, 3.7.B.I.c, 3.7.B.I.e, be determmed to be operable by i 3.7.B.2.c, and 3.7.B.2.e if Speci6 cation performance of an instrument 3.9.A.1 and 3.9.A.2.a are satisfied. calibration and by verifying j tripping of the circuit breakers

4. From and aAer the date that one of the diesel upon the simulated conditions j

.ai.; ors or associated emergency buses for automatic actuation of the and either the shutdown or startup protective relays within the 5 transformer power source are followmglimits: j Overvoltage 5132 volts Undervoltage 2108 volts Underfrequency > 57Hz {: i i i j Amendment No. "", T. M5. ?!?,170 j 314.94 l

___.___7_ l q 1, BASES: 3/4.7 CONTAINMENT SYSTEMS (Cont.) j ] Tests ofimpregnated charcoal idatical to that used in the filters indicate that a shelflife of five years leads j to only minor decreases in methyl iodide nuoval efEciency. Hence, the frequency oflaboratory carbon sample analysis is adequate to demonstrate acceptabihty. Since adsorbers must be removed to perform this analysis this Owy also mamuses the systan out of service time as a resuk of survallance testing In addition, although the halogenated hydrocarbon testag is basically a leak test, the adsorbers have charcoal l cfknown M and holdmg capacity for elemstal iodme and/or methyl iodide, the testag also gives an imbcanon of the relative efficasocy of the installed system 'Ibe 31 day requiranent for the ascertaining of i test resuhs ensures that the ability of the charcoal to perforndts designed function is danonstrated and j knownin a tunely manner. i 'Ibe required Standby Gas Treatment System ihm rate is that flow, less than or equal to 4000 CFM which is needed to inmintam the Reactor Buildag at a 0.25 inch of water negative pressure under calm wind conditions 'Ihis capability is adequately demonstrated duru g W7 antninmet Leak Rate Testmg C performed pursuant to Techmcal S +4' =:on 4.7.C.I.c. i J ] 'Ibe test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests q are not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly. 'Ibe filter testing is pio..-4 pursuant to appropriate procedures reviewed and approved by the 4 Operations Review Committee pursuant to Section 6 of these Technical Specifications 'Ihe in-place j testing of charcoal filters is & u...d by infecting a halogensted hyd.ostw. into the system upa.wn of f l the charcoal adsorbers. Measurements of the nancentration upstream and downstream are made. 'Ibe ratio 1 of the inlet and outlet cancantrations gives an overall indication of the leak tightness of the system A i samlar procedure substituting dioetyl ak+k 1='a for hale== ' hydrocarbon is used to test the HEPA fikers. 4 4 Pressure drop tests across filter and adsorber banks are performed to detect pluggag or leak paths though j the filter or adsorber media. Ching the relatively short times the fans will be run for test purposes, ~ pluggag is unhkely and the test interval of once per operatmg cycle is ra==anahle. Systan drains and housing gasket doors are designed such that any leakage would be inleakage from the Standby Gas Treatment System Room " Ibis ensures that there will be no bypass ofprocess air around the filters or adsorbers 1 ^ Only one of the two Standby Gas Treatmmt Systans (SBGTS) is needed to maintam the sacandary ennenmaust at a 0.25 inch of water negative pressure upon contamment isolation. If one system is made or found to be inoperable, there is no immedate threat to the cantainment system gio....w.ce and reactor cperation or refuehas activities may continue while repairs are bemg made. In the event one SBGTS is l isoperable, the redundant system's active companants will be verified to be operable wittun 2 hours. This j 4 =ihata=*= tan the availability of the operable systen andjustifies nant=nad reactor or refuehag operations. ~ e j l Dunns.4.ig outages, if the inoperable train is not restored to operable status within the required completion time, the operable train should unmedately be placed in operation. 'Ihis action ensures that the i runnining train is operable, that no failures that could prevent automatic actuation have occurred, and that j any other failure would be readdy detected An alternative is to suspend fuel movement, thus, placing the i plant in a condition that mamuses risk. i i j Amendesat Ns. 4tl 1M/Mf,170 g 314.710

, - - ~ _. _. - l 3/4.7 CONTAINMENT SYSTEMS (Cont.) i l B.2 Control Room Egh EfEciency Air Fdtration Systen (Coat.) i i The test frequencies are adequate to detect equipment detenoration prior to sigmficant defects, but the tests are not frequent enough to load the fikers or adsorbers, thus re:lucing their reserve capacay too quickly. } The filter testag is pt _ pursuant to appropnate procedures reviewed and approwd by the W3 Revww Committee pumat to Section 6 of these Technical W.1he in9 ace 1 testing of charcoal filters is performed by injectag a halogensted hydrocarbon into the systen upstroom of the charcoal adsorbers. Measurements of the concentration p.a. and downstream are made. The ratio j of the inlet and outla c=rmarrations gives an overall indication of the leak tuhaness of the system A l similar procedure suW=- dioctyl phthale** for 'Ey- ^-i hydrocarbon is used to test the HEPA i filters. l Air flow through the filters and ciecoal adsorbers for 15 minutes each month assures operability of the system Since the system heaters are automatically controlled, the air fkang through the filters and [ adsorbers will be 570% relative humxhty and will have the desired drying effect 1 i l If one train of the system is made or found to be inoperable, there is no immedate threat to the control room, and reactor operation or fuel handhng may contmue for a hmited penod of time while repairs are bemg made. In the event one CRHEAF train is inoperf ble, the rah =daar system's active w.A.s will be venfied to be operable within 2 hours. During refuehag outages, if the inoperable train is not restored to operable status within the required completion time, refuchng operations may r=riane provuled the operable CRHEAF train is placed in the pressurization mode daily.1his action ensures that the remainmg train is operable, that no failures that would prevent actuation will occur, and that any active failure will be i readdy detected An alternative is to suspend activities that present a potential for releasing radioactivity that might require isolation of the control room. If both trams of the CRHEAF systan are inoperable, the reactor will be brought to a condition where the Control Room High Efficiency Air Filtraten System is not [ required. 5 1 i i i i i j l 1 i 3 i i 4 I t I i 1 { AmendmentNo.O T,170 B314.712 i i 1 4 . -}}