ML20137W661

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Proposed Tech Specs,Relocating SR for Attaining Negative Pressure in Enclosure Bldg (4.6.5.1.d.3) from TS 3.6.5.1, Enclosure Bldg Filtration Sys to TS 3.6.5.2, Enclosure Bldg Integrity (4.6.5.2.2)
ML20137W661
Person / Time
Site: Millstone Dominion icon.png
Issue date: 04/10/1997
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20137W650 List:
References
NUDOCS 9704180171
Download: ML20137W661 (27)
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DQGkttlRQJHb13fi B16344 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Enclosure Building Marked Up Pages 1

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April 1997

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-DEFINITIONS PhE SECTION J

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D. e g.. ming integrity.........................

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LReactor Trip System Response Time..........

....s4.........

1 Engineered Safety Feature Responie Time............s...s....

1-5 Physics Tests...............................................

1-6

~ Unrodded Integratid Radial Peaking Factor - F..............

1-6

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-Source Check...............................................

1-6 i

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- Radiological Effluent Monitoring and_0ffsite Dose

, Calcul ation Manual (REM 00CM).......... 'c..

1-6 Radioactive Waste Treatment Systems.........................

1-6 4

Purge - Purging..............................................

1-6 Venting.s...............................................

1-8 '; *', 5 j

Member (s) of the Public.........................^....'..'.....

1.8 Site Boundary...............................................

1-8 i

Unrestricted Area..............................c.........'...

1-8 I

Storage Pattern.............................................

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?HILLSTONE' UNIT'2-'

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Amendment No. 7A4, JJJ, JJ7, 0030:

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1 February 14, 1992 4

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g LIMITING CONDITIONS-FOR OPERATION AND SURVEf SECTION 3/3.6 CONTAINMENT SYSTENS 3/4 6-1 PRIMARY CONTAINMENT...............................

3/4 6-1' 3/4.6.1~

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. Containment Integrity.............................

3/46-2 l

I

-Containment Leakage...............................

3/4 6-6 Containment Air Locks.............................

3/4 6-8 Internal Pressure.................................

3/4 6.

Air Temperature...................................

3/4 6-10 Containment Structural Integrity..................

3/4 6-12 DEPRESSURIZATION AND COOLING SYSTEMS...........

3/4 6-12 3/4.6.2 Containment' Spray System..........................

3/4;6.I4 i

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Containment Air Reci rcul ati on System..............

3/4 6-15 CONTAINMENT ISOLATION VALVES......................

3/4 6-19

, 3/4.6.3

[, Containment Ventil ation System.'.i................

3/4 6-20 COMBUSTIBLE GAS CONTROL...........................

3/4 6-20 y..

,3/4.6.4 Hydrogen Monitors.................................

3/4 6-21 j

El ectric Hydrogen Recombiners.= M.................

i 3/46-23 lc Hydrogen Purge System.............................

3/46-24 l

Post-Incident Recirculation Systems...............

3/46-25 SECOND ARY CONT AINMENT.........'..................

3/46-25 3/4.6.5 Enclosure Building Filtration System..............

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Enclosure Building ht:;d t,C................

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.Ohtober 12, 1990 Q).

DEFINITIONS AXIAL SHAPE INDEX The AXIAL SHAPE INDEX (Ye) used for normal control and indication _ is 1.23

_ the power leve1' detected by thb lower excore nuclear instrument detectors (L) 1ess-the power level detected by the upper excore nuclear instrument detectors The AXIAL SHAPE INDEX (Y,)

(U) divided by.the sum.of these power levels.

used for the trip and pretrip signals in the reactor protection system is_ the.above i

value (Ye) modified by an appropriate multiplier (A) and a constant (B) to determinh the true core axial power distribution for that channel.

YI " A E+B Y

E " L+U.

' CORE OPERATING LIMITS ~ REPORT

.1.24.The CORE' OPERATING L1 HITS REPORT is the. unit specific document that provides the core operating limits for the current operating reload cycle.

These cycle specific core operating limits shall be determined for each reload Plant _ operation within these cycle in accordance with Specification 6.9.1.7.

operating limits is addressed in indivi. dual specifications?

t ENCL 0'SURE BullDING INTEGRITY - Df4ErgD I

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--1.25 O'CLCSURE S"ILDIPO!PTECP!" ch:11 cxist when:

E:ch decr in cach acce+s-open n; is c1"ad " cept ".:n th; i

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--a :::s-epening is being used f+r nort:1 tr:n:it :ntry 3M "it

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The :n:1csere-building fiiiratiun ystein is Orf"ABLE.

1.25.2 REACTOR TRIP SYSTEM RESPONSE TIME The REACTOR TRIP SYSTEM RESPONSE TlHE shall be the time interval 1.26 from when the monitored pa'rameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

ENGINEERING SAFETY FEATURE RESPONSE TIME lli27 The ENGINEERED SAFETY FEAT RE RESPONSE TlHE.shall be that time, interval from when the' monitored parameter exceeds its ESF actuation'setpo' int

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at the channel = sensor until the ESF equipment is capable of f.

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i AmendmentNo.E,Us,/k MILLSTONE - UNIT 2-1 e

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February 22, 1982 i g.

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~6' CONTAINMENT SYSTEMS i

3/4.6.5 SECONDARY CONTAINMENT ENCLOSURE BUILDING FILTRATION SYSTEM.

P LIMITING CONDITION FOR CPERATION Y

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f" 3.6.5.1/shall be OPERABLE.Two separate and in' depende

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L APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one /nclosure guilding /iltration#:ytte inoperable, restore the

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I inoperable sy:t=. to OPERABLE status within 7 days or be in COLD SHlIT-

'DOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

ha s.v SURVEILLANCE REQUIREMENTS U"'N v

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4.6.5.1 Each Anclosure guilding /iltration eystem shall be demonstrated f

OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by initiat-a.

ing, frem the control room, flow through the HEPA: filter and charcoal adsorber train and verifying that the train operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on.

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At least once per 18 months or (1) after any structural maintenance 3

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on the HEPA filter or charcoal adsorber housings. or (2) following rl 61 painting, fire or chemical release in any ventilation zone comuni / j l

cating with the,2y t= by:

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May 23, 1994 COMfAINMENT SYSTEMS SURYEILLANCE REQUIRDIENTS (Continued)

I 1.

Verif'ying that the cleanup -:y:t= satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a.

C.5.c and C.S.d of Regulatory Guide 1.52, Revision 2,.4 arch 1978, and the 4y+ tem flow rate is 9000 cfm

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10%.

2.

Verifying within 31 days efter removal that a laboratory analysis of a representative carbon saple obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory /

Position C.6.a latory Guide 1.52, Revision 2, March 1978.*

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Verifying a Oy:t= flow rate of 9000 cfm 10% during y:t=

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operation when tested in accordance with ANSI N510-1975.

After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying s

c.

within 31 days after removal that a laboratory analysis of a representa-tive carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory - Guide 1.52, Revision 2,

March 1978, meets the :

laboratory testing criteria of Regulatory Position C.6.a of Regulatory.,: l Guide 1.52, Revision 2, March 1978.*

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.d., At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is s

6 inches Water Gauge while I

operating the=sy:ta ate of 9000 cfm i 10%.

2.

Verifying that the syste starts on an Enclosure Building Filtra- /

tion Actuation Signal (EBFAS).

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' rifying thd each syst.em' produces a egative pre (ure of grp[ter I

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ethan or,4 qual to 0,25 inces W.. in the E losure Building Filtra pon Region within (1) ming e after an AS.

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After each complete or partial replacement of a HEPA filter bank by e.

verifying that the HEPA filter banks remove greater than er squal to 99% of the DOP when they are tested in-place in accordance 'with ANSI N510:1975 while operating the sy:t= at a flow rate of 9000 cfm

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.i 10%.

a+wme, ASTM D3803-89 shall be used in place of ANSI H509-1976 as referenced in i

table 2 of Regulatory Guide 1.52. The laboratory test of charcoal should be l

conducted at a temperature of 30*C and a relative humidity of 95% within the M' tolerances specified by ASTM D3803-89.

Additionally, the ~ charcoal samphL shall. have a removal efficiency of ;t 95%.

MILT. STONE - UNIT 2 3/46-26 Amendrent No. 7J, 77,//I 0132

February 22, 198,2

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

After each etimplete or. partial replacement of a charcoal adsorber f.

bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 61 while operating the sy:ts. at a. flow rate of 9000 cfm + JO%.

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CONTAINMENT SYSTEMS ENCLOSURE BUI'LDIN'G -I!4TEGRITY LIMITING CONDITION-FOR OPERATION Th e Enc /csuse BaiI./,,,, s-Aat/ d< oFEgagth I-3.6.5.2 Er;LOSUR: 0"!LO!:;0 I;iTEGRITY 3:.11 L. m hteir.:d. (

APPLICABILITY _: MODES 1, 2, 3.and 4.

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9 "ithet ENCLOSURE BUI'_DI9: !!CEORIT restore Et; CLOS"P.: SJILDINGIFTECP.TY-

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within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

SURVEILLANCE REOUIREMENTS (MER AArt2 TV or' tac Enchute Aa:LAr)r

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d [t;CLO;UR: CUILDI;;0 I;;TEGR;TY shall be demonstrated at least f@

once per 31 days by verifying that-c;d d;;r 'each access opening is g:':-

I 4.6.5.2 closed except when the access opening is being used for normal transit h

entry and exit.

h,b, C,9,3 Al-l card once ys /Tnsenflor ve/ify feeb Enc /csai< Bui/Jidy FiHra% pa,,,, y,,2 aces.

of y/edu y%. o, que / -A,

. a 11cya he picswe O 9 S* inAes (U. 6. is the Enc /crw& Aoi/,Ja, h

f, /fra-he.v 6fe,ye~ wn% 2 mi,va fe a M > an Enc /csa<c Bud.l',13 & ffrahe.v /9c+ue k.v Saj,w /.

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February 22,I1982-4

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REFUELING' OPERATIONS..

y STORAGE POOL AREA VENTILATION-SYSTEM '- FUEL STORAGE 3'+

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LIMITING ~bONDITIONFOROPERATION'

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3.9.15'i At least one Enclosure Building Filtration-Sy:t - shall be _

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l OPERABLE and capable-of automatically initiating' operation in-the auxil-y c i.

iary exhaust mode and.. exhausting through HEPA~ filters 'and cha', coal adtorbers on a storage pool area high radiation' signal.

APPLICABIO TY:-.WHENEVER' IRRADIATED FUEL IS-IN THE STORAGE POOL.

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ACTIONi With the requirements:of the'above specification not satisfied, suspend all e

operations-involving movement of fuel within the. storage pool or crane operation with loads over. the storage. pool until at least one ;;st fu:F

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t:n;e.pcel *;:nt'hth: :y:t:r is restored to-OPERABLE statuk Ens /ozan Bash /idy

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SURVEILLANCE REQUIREMENTS n,g 4.9.15' The above required Enclosure Building Filtration Sy:t:r shall

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.n be demonstrated OPERABLE:

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At least once per 31 days on a STAGGERED TEST BASIS by initiating, a..

from the control room, flow through the HEPA filters and charcoal g/

.adsorbers and verifying that the +ys.tm perates for at least

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,10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with 'the heaters on.

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.At least once per 18.manths or-(1) after any structural maintenance' 6'

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l on the HEPA filterf or charcoal adsorber housing's, or (2) fo? lowing j

fB painting.: fire er chemical release in any v'entilation zone communi-jj-n

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May 23,.1'994 REFUELING OPERATIONS i

SURVEILLANCEREQUIREMENTS(Continued)

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' Verifying that the cleanup y:t= satisfies the in-place, testing

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acceptance criteria and uses the test procedures of Regulatory Positions C.S.a, C.5.c and C.S.d of. Regulatory Guide 1.52, Revi-sion 2, March 1978, and the-:y:t=

e is 9000 cfm 10%.

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2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.

Regulatory Guide 1.52, Revision 2, March 1978.*

I 3.

Verifying a -sy:t= flow rate of 9000 cfm 10% during ys t =-

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operation when tested in accordance with ANSI N510-1975.

fraw After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying c.

within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.*

d.

At least once per 18 months'by: '

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is s 6 inches Water Gauge while operating the syst= at a flow rate of 9000 cfm 10%.

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(+,a,.8 2.

Verifying thatjon a Spent Fuel Storage Pool Area high radiation signal, the syste automatically starts (unless already operating)

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and directs its exhaust flow through the HEPA filters and charcoal adsorber banks.

After each complete or partial replkcement of a HEPA filter bank by e.

verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the +ysten at a flow rate of 9000 cfm 10%.

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.a ASTM D3803-89 shall be used in place of ANSI H509-1976 as referenced in I

table 2 of Regulatory Guide 1.52. The laboratory test of charcoal should l

be conducted at a temperature of 30'C and a relative humidity of 95%

within the tolerances specified by ASTM D3803-89.

Additionally, the charcoal sample shall have a removal efficiency of 2 95%.

J AmendmentNo.77.h MILLSTONE - UNIT 2 3/49-17 0134 o

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Februa ry' T2,1982 a

REFUELING OPERATIONS SURVEILLANCE REOUIREMENTS (Continued)

I After each complete or partial replacement of a charcoal adsorber

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bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975.

61 while operating the +yh at a flow rate of 9000 cfm +,10%..

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August 1,1975

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CONTAINMENT SYSTEMS BASES _

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3/4.6.5 SECONDARY CONTAINMENT/

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3/4.6.5.1 ENCLOSURE BUILDING 4'ENTILATION SYSTEM E

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TheOPERABILITYoftheynclosureJuildingventil:tionsystednsures l-that, containment leakage occurring during LOCA conditions into the annulus

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will be filtered through the HEPA filters and charcoal-ab;srber, trains prior ' 4 d cme,-

J to discharge to the atmosphere. This requirement is necessary to meet tne assumptions used in the accident analyses and limit the site boundary radi-I ation doses to'within the limits of 10 CFR 100 during LOCA conditions.

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0"NA" 3/4.6.5.2 ENCLOSURE BUILDING INTECRITY

-EfictOSURE OUILDINC ISECRITY-ensures that the releases of radioactive

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materials from the primary containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accide

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j analyses. This restriction, in conjunction with operation of the closure (jtuilding ventd1:tien, system, will limit the site boundary radiation doses to within the" limits of 10 CFR 100 during a:cident conditions.

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.REFUELI'NG OPERATIONS BASES I

3/4.9.13 STORAGE POOL RADIATION MONITORING.

The OPERABILITY of the storage 1ool radiation monitors ensures that I

sufficle'nt radiation sionitoring capasility is available'to detect excessive radiation levels.resulting from 1) the inadvertent lowering of the storage pool water level or 2) the release of'setivity from an irradiated fuel i

assembly.

3/4.9.14 & 3/4~.9.15 STORAGE POOL AREA VENTILATION SYSTEM The limitations.on the.. storage pool area ventilation system ensures that all radioactive material released from' an irra'diated fuel assembly will be

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filtered through the,'HEPA filters and charcoal adsorber prior to discharge to The OPERABILITY of this system and the resulting iodine

. the atmosphere. removal capacity are consistent with the assumptions of the accide WSWh 4.9.16 SHIELDED CASK The limiiations of'.this specification ensure that in an event of a cask tilt acc-ident 1) the doses from ruptured fuel assemblies will be within the assumpti'ns of the safety analyses, 2) X,ff will remain f.95.

e 3/4.9.17 MOVEMENT OF FUEL IN SPENT FUEL POOL.

J The" limitations of this specification ensure that, in the event of a fuel assembly or 'a consolidated fuel storage box drop accident into a Region 8 or C will remain rack ~1ocation completing a 4-out-of-4 fuel assembly geometry, X,ff 3 0.95.

3/4.9.18 SPEfR FUEL POOL - REACTIVITY CONDITION 4_

The limitations described by Figures 3.9-la, 3.9-lb, and 3.9-3 ensure

/

v that the reactivity of fuel assemtilies and cons.olidated fuel storage boxes, introduced into the Region C spent fuel racks, are conservatively within the assumptions of the safety analysis.

The limitations described by Figure 3.9-4 ensure that the reactivity of i

the fuel assemblies, introducted into the Regien A spent fuel racks, are tenservatively within the assumptions of the safety analysis.

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4 MILLSTONE - UNIT 2 B3/49-3 Amendment No. JJ, JJJ, JJJ,

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INSERT A 4

The laboratory testing requirement for the charcoal sample to have a removal efficiency of 2 95% is more conservative than the elemental and organic iodine removal efficiencies of 90% and 70%, respectively, assumed in the DBA analyses for the EBFS charcoal adsorpers in the Millstone Unit 2 Final Safety Analysis Report. A removal efficiency acceptance criteria of 2 95% will ensure the charccal has the capability to perform its intended safety function throughout the length of an operating cycle.

INSERT B One Enclosure Building Filtration System train is required to establish a negative pressure of 0.25 inches W.G. in the Enclosure Building Filtration Region within one minute after an Enclosure Building Filtration Actuation Signal is generated. The one minute time requirement does not include the time necessary for the associated emergency diesel generator to start and power Enclosure Building Filtratim System equipment.

s To enable the Enclosure Building Filtration System to establish the required negative pressure in the Enclosure Building, it is necessary to ensure that all Enclosure Building access openings are closed. For double door access openings, only one door is required to be closed and latched, except for normal passage. For single door acceu openings, that door is required to be closed and latched, except for normai ps ssage.

A door is OPERABLE when it is capable of automatically closing and htching. If the required door is not capable of automatically closing and latching, the door rnust be maintained closed and latched or personnel may be stationed at the door to ensure that the door is closed and latched after each transit through the door. Otherwise, the access opening (door) should be declared inoperable and the appropriate technical specification action statement entered.

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1 Docket. No. 50-336 B16344 A

Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications l

Enclosure Building Retyped Pages c

f i

4 A

l April 1997

~.

1HQEX DEFINITIONS t

SECTION EAGE I

Reactor Trip System Response Time................ 1-5 Engineered Safety Feature Response Time.............

1-5 Physics Tests...........................

1-6 Unrodded Integrated Radial Peaking Factor - F, 1-6 Source Check 1-6 Radiolgical Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) 1-6 Radioactive Waste Treatment Systems...............

1-6 Purge - Purging.........................

1-6 Venting.............................

1 j Member (s) of the Public.....................

1-8 Site Boundary..........................

1-8 Unrestricted Area........................

1-8 i

Storage Pattern................. -.......

1-8 1

4 1

MILLSTONE - UNIT 2 II Amendment No. 7pf,-JJJ, JJ7..

I Jife 191, i

INDEX l

LIMITING COMITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION fa(if.

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.................

3/4 6-1 Containment Integrity................

3/4 6-1 Containment Leakage.................

3/4 6-2 Containment Air Locks 3/4 6-6 Internal Pressure 3/4 6-8 Air Temperature...................

3/4 6-9 Containment Structural Integrity 3/4 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4 6-12 Containment Spray System _

3/4 6-12 Containment Air Recirculation System 3/4 6-14 3/4.6.3 CONTAINMENT ISOLATION VALVES 3/4 6-15 Containment Ventilation System 3/4 6-19 3/4.6.4 COMBUSTIBLE GAS CONTROL 3/4 6-20 Hydrogen Monitors 3/4 6-20 Electric Hydrogen Recombiners - M..........

3/4 6-21 Hydrogen Purge System................

3/4 6-23 Post-Incident Recirculation Systems 3/4 6-24 3/4.6.5 SECONDARY CONTAINMENT................

3/4 6-25 Enclosure Building Filtration System 3/4 6-25 Enclosure Building 3/4 6-28 l

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NILLSTONE - UNIT 2 VII Amendment No. Jpf, JJJ, ONC

L l

e DEFINITIONS f

AXIAL SHAPE INDEX 1.23 The AXIAL SHAPE INDEX (Yg) used for normal control and indication is the power level detected by the lower excore nuclear instrument detectors (L) less the power level detected by the upper excore nuclear instrument detectors (U) divided by the sum of these power levels. The AXIAL SHAPE INDEX (Y) used for the trip and pretrip signals in the reactor protection system is the above value (Yg) modif'ed by an appropriate multiplier (A) and a constant (B) to determine the true core axial power distribution for that channel.

Y, =

Y, = A Y, + B CGRE OPERATING LIMITS REPORT 1.24 The CORE OPERATING LIMITS REPORT is the unit specific document that provides the core operating limits for the current operating reload cycle.

These cycle specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.7. Plant operation within these operating limits is addressed in individual specifications.

DELETED ENCLOSURE BUILDING INTEGRITY REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

ENGINEERING SAFETY FEATURE RESPONSE TIME 1.27 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of 7

NILLSTONE - UNIT 2-1-5 Amendment No. 77, 177 JJp, O391' 1

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i o

CMTAIMENT SYSTEMS I

3/4.5.5 SECOMARY CONTAIMENT ENCLO$tRE SUILDINR FILTRATION SYSTEN LIMITING COMITION FOR OPERATION e

L i

j 3.6.5.1 Two separate and independent Enclosure Building Filtration Trains l l

'shall be OPERABLE.

1 APPLICABILITY: N00ES 1, 2, 3 and 4.

i ACTION:'

With one Enclosure Building Filtration Train inoperable, restore the inoperable train to OPERABLE status within 7 days or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

i SURVEILLANCE REQUIRENENTS 4.6.5.1 Each Enclosure Building Filtration Train shall be demonstrated l

l OPERA 8LE-a.

At least once per 31 days on a STAGGERED TEST BASIS by initiat-ing, from the control room, flow through the HEPA filter and charcoal atesorber train and verifying that the train operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on.

b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal absorber housings, or (2) following painting, fire or chemical release in any ventilation zone communi-cating with the train by:

l 1

NILLSTONE - UNIT.2 3/46-25' Amendment No.

0202.

CONTAIMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.

Verifying that the cleanup train satisfies the in-place testing l acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the train flow rate is 9000 cfm i 10%.

2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.*

3.

Verifying a train flow rate of 9000 cfm 10% during train l

operation when tested in accordance with ANSI N510-1975.

c.

After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adscrber operation by verifying within 31 days after removal that a laboratory analysis of a representa-tive carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.*

d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is 5 6 inches Water Gauge while operating the train at a flow rate of 9000 cfm i 10%.

l 2.

Verifying that the train starts on an Enclosure Building Filtra-l tion Actuation Signal (EBFAS).

I e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI 2

N510-1975 while operating the train at a flow rate of 9000 cfm l

l 1 15.

1 i

ASTM D3803-89 shall be used in place of ANSI N509-1976 as referenced in table 2 of Regulatory Guide 1.52. The laboratory test of charcoal should be conducted at a temperature of 30*C and a relative humidity of 95% within the tolerances specified by ASTM D3803-89.

Additionally, the charcoal sample shall have a removal efficiency of 2 95%.

MILLSTONE - WIT 2-3/4 6-26 Amendment No. JJ, 77, J7),

0292

  • ~

.+

O e

CONTAlletENT SYSTEMS SURVEILLANCE REQUIRENENTS (Continued) f.

After each complete or partial replacement of a charcoal absorber 1

bank by verifying that the charcoal absorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the train at a flow rate of 9000 cfm i 10%.

l NILLSTONE - UNIT 2 3/4 6-27 Amendment No.

0292

s CONTAINNENT SYSTEMS ENCLOSURE BUILDING l

LINITING ColWITION FOR OPERATION 3.6.5.2 The Enclosure Building shall be OPERABLE.

l APPLICABILITY:

NODES 1, 2, 3 and 4.

ACTION:

With the Enclosure Building inoperable, restore the Enclosure Building to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

SURVEILLANCE REQUIRENENTS 4.6.5.2.1 OPERABILITY of the Enclosure Building shall be demonstrated at least l once per 31 days by verifying that each access opening is closed except when the access opening is being used for normal transit entry and exit.

4.6.5.2.2.

At least once per 18 months verify each Enclosure Building Filtration Train produces a negative pressure of greater than or equal to 0.25 inches W.G. in the Enclosure Building Filtration Region within 1 minute after an Enclosure Building Filtration Actuation Signal.

NILLSTONE - UNIT 2 3/4 6-28 Amendment No.

0292

. _ _ _ _ _ _.. _ _ _ _ _.. ~ _ _ _ _. _. _

i REFUELING OPERATIONS i

STORARE P00L AREA VENTILATION SYSTEN - FUEL STORAGE LIMITING COMITION FOR OPERATION 3.9.15 At least one Enclosure Building Filtration Train shall be l

OPERABLE and capable of automatically initiating operation in the auxil-lary exhaust mode and exhausting through HEPA filters and charcoal adsorbers on a storage pool area high radiation signal.

APPLICABILITY: WHENEVER IRRADIATED FUEL IS IN THE STORAGE POOL.

ACTION:

With the requirements of the above specification not satisfied, suspend all

' operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one Enclosure Building Filtration Train if, restored to OPERABLE status.

i SURVEILLANCE REQUIRENENTS 4.9.15 The above required Enclosure Building Filtration Train shall l

be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the train operates for at least l

i 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on.

b, At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communi-cating with the train by:

l 1

i NILLSTONE - UNIT 2 3/4 9-16 Amendment No. 71, 0293

l...:

REFUELING 0PERF"11

(

SURVEILLANCE RL

.AENENTS (Continued) 1.

Verifying that-the cleanup train satisfies the in-place testing l

acceptance criteria and uses the test procedures of Regulatory Positions C.5.a. C.5.c and C.S.d of Regulatory Guide 1.52, Revi-sion 2, March 1978, and the train flow rate is 9000 cfm i 10%.

l 2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, i

March 1978, meets.the laboratory testing criteria of Regulatory 4

Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.*

i 3.

Verifying a train flow rate of 9000 cfm 10%duringtrainoperationl when tested in accordance with ANSI N510-1975.

I c.

After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying 1

within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position i

C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory i

Guide 1.52, Revision 2, March 1978.*

j d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA l

filters and charcoal adsorber banks is s 6 inches Water Gauge i

while operating the train at a flow rate of 9000 cfm 10%.

l 2.

Verifying that on a Spent Fuel Storage Pool Area high radiation signal, the train automatically starts (unless already operating) l l

and directs its exhaust flow through the HEPA filters and charcoal adsorber banks.

e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the train at a flow rate of 9000 cfm i 10%.

l L

ASTM D3803-89 shall be used in place of ANSI N509-1976 as referenced in table 2 of Regulatory Guide 1.52. The laboratory test of charcoal should be conducted at a temperature of 30*C and a relative humidity of 95%

within the tolerances specified by ' ASTM D3803-89.

Additionally, the

. charcoal' sample shall have a removal efficiency of it 95%.

gL,LSTONE-UNIT 2.

3/4 9-17 Amendment No. 77, M,

)

1 REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than

)

or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating tha train at a flow rate of 9000 cfm 10%.

l l

4 E

I NILLSTONE - UNIT 2 3/4 9-18 Amendment No.

0293 i

.. g' 4

e'

' CONTAllNIENT SYSTEMS mn 3/4.6.5 SECONDARY CONTAllMENT 3/4.6.5.1 ENCLOSURE BUILDING FILTRATION SYSTEM l

The OPERABILITY of the Enclosure Building Filtration System ensures l

i that containment leakage occurring during LOCA conditions into the annulus will be filtered through the HEPA filters and charcoal adsorber trains prior l

to discharge to the atmosphere. This requirement is necessary to meet the assumptions used in the accident analyses and limit the site boundary radia-tion doses to within-the limits of 10 CFR 100 during LOCA conditions.

The laboratory testing requirement for the charcoal sample to have a removal efficiency of 2 95% is more conservative than the elemental and j

organic iodine removal efficiencies of 90% and 70%, respectively, assumed in the DBA analyses for the EBFS charcoal adsorbers in the Millstone Unit 2 Final Safety Analysis Report. A removal efficiency acceptance criteria of 2 95%

.will ensure the charcoal has the capability to perform its intended safety function throughout the length of an operating cycle.

)

i 3/4.6.5.2 ENCLOSURE BUILDIE l

1 The OPERABILITY of the Enclosure Building ensures that the releases of l

radioactive materials from the primary containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.

This restriction, in conjunction with operation of the Enclosure Building Filtration System, will limit the site boundary radiation l

doses to within the limits of 10 CFR 100 during accident conditions.

One Enclosure Building Filtration System train is required to establish a negative pressure of 0.25 inches W.G. in the Enclosure Building Filtration Region within one minute after an Enclosure Building Filtration Actuation Signal is generated. The one minute time requirement does not include the time necessary for the associated emergency diesel generator to start and power Enclosure Building Filtration System equipment.

To enable the Enclosure Building Filtration System to establish the required negative pressure in the Enclosure Building, it is necessary to ensure that all Enclosure Building access openings are closed.

For double 4

door access openings, only one door is required to be closed and latched, except for normal passage.

For single door access openings, that door is required to be closed and latched, except for normal passage.

A door is OPERABLE when it is capable of automatically closing and latching.

If the required door is not capable of automatically closing and latching, the door must be maintained closed and latched or personnel may be stationed at the door to ensure that the door is closed and latched after each transit through the door. Otherwise, the access opening (door) should be declared inoperable and the appropriate technical specification action statement entered.

4 MILLSTONE - UNIT 2 5 3/4 6-5 Amendment No.

02M

\\

,a' REFUELING 0PERATIONS BASES 3/4.9.13 STORAGE POOL RADIATION MONITORING The OPERABILITY of the storage pool radiation monitors ensures that sufficient radiation monitoring capability is available to detect excessive radiation levels resulting from 1) the inadvertent lowering of the storage pool water level or 2) the release of activity from an irradiated fuel assembly.

3/4.9.14 & 3/4.9.15 STORAGE POOL AREA VENTILATION SYSTEM The limitations en the storage pool area ventilation system ensures that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

The laboratory testing requirement for the charcoal sample to have a removal efficiency of 2 95% is more conservative than the elemental and organic iodine removal efficiencies of 90% and 70%, respectively, assumed in the DBA analyses for the EBFS charcoal adsorbers in the Millstone Unit 2 Final Safety Analysis Report. A removal efficiency acceptance criteria of 2 95%

will ensure the charcoal has the capability to perform its intended safety function throughout the length of an operating cycle.

5 3/4.9.16 SHIELDED CASK t

The limitations of this specification ensure that in an event of a cask s

tilt accident 1) the doses from ruptured fuel assemblies will be within the assumptions of the safety analyses, 2) Km will remain s.95, 3/4.9.17 MOVEMENT OF FUEL IN SPENT FUEL P001 The limitations of this specification ensure that, in the event of a fuel assembly or a consolidated fuel storage box drop accident into a Region B or C rack location completing a 4-out-of-4 fuel assembly geometry, K, will remain 1 0.95.

3/4.9.18 SPENT FUEL POOL - REACTIVITY CONDITION The limitations described by Figures 3.9-la, 3.9-lb, and 3.9 3 ensure that the reactivity of fuel assemblies and consolidated fuel storage boxes, introduced into the Region C spent fuel racks, are conservatively within the assumptions of the safety analysis.

The limitations described by Figure 3.9-4 ensure that the reactivity of the fuel assemblies, introducted into the Region A spent fuel racks, are conservatively within the assumptions of the safety analysis.

MILLSTONE - UNIT 2 B 3/4 9-3 Amendment No. 77, 197, JJ7.

om 191,JF7,J11

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