ML18086B592

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Proposed Tech Spec Changes & Revisions Re Fire Barrier Penetration Requirements for Unit 1 & Radiation Monitoring Table Changes for Units 1 & 2
ML18086B592
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/22/1982
From:
Public Service Enterprise Group
To:
Shared Package
ML18086B590 List:
References
NUDOCS 8207290133
Download: ML18086B592 (10)
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Jf\\.1 LIMITING CONDITIONS FOR OPERATION 3.7.11 A11 penetration fire barriers protecting safety related areas shal1 be functional.

APPLICABILITY:

At 111 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 wfthin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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.

~-

e SALEM

  • UNIT 1

~ - -

8207290133 020622 PDR ADOCK 05000272 P

PDR I

3/4 7-42 Amendment f4o. 11

I PLANT SYSTEMS 3/4.7. 11 PENETRATION FIRE BARRIERS LIMITING CONDITION FOR OPERATION 3.7. 11 All fire barrier penetrations (including cable penetration barriers, firedoors and fire dampers), in fire zone boundaries, protecting safety related areas shall be functional.

APPLICABILITY:

At all times.

ACTION:

a.

With one or *ore of the above required fire barrier penetrations non-functional, within one hour either establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the non-functional fire barrier and establish an hourly fire watch patrol.

Restore the non-functional fire barrier penetration(s) to functional status within 7 days or, in lieu of any other report required by Specification 6.9. 1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action. taken, the cause of the non-functional pene-tration and plans and schedule for restoring the fire barrier pene-tration(s) to functional status.

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:

a.

At least once per 18 months by a visual inspection, and

b.

Prior to returning a penetration fire barrier to functional status following repairs or maintenance by the performance of a visual inspection of the affected penetration fire barrier(s).

SALEM - UNIT 2 3/4 7-37

PROPOSED REVISION TECHNICAL SPECIFICATIONS APPENDICES 'A' AND 'B' SALEM UNIT NOS. l AND 2 DESCRIPTION OF CHANGE LCR NO. 81-07 (Rev. 2)

The Safety Technical Specifications, Tables 3.3-3, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION, 3.3-6, RADIATION MONITORING INSTRUMENTATION, and the Environmental Technical Specifications, Table 2.3-4, SALEM GASEOUS WASTE SYSTEM -

LOCATION OF PROCESS AND EFfLUENT MONITORS AND SAMPLERS REQUIRED BY TECHNICAL SPECIFICATIONS, should be revised to agree with as built conditions on Unit No. 2 and with the identical planned modifications for Unit No. 1.

The revision should be made to conform to the attached marked-up pages which i.nclude the new Plant Vent Monitors R41A, B, and c.

REASON FOR CHANGE The Tables should reflect the plant radiation monitoring system as it has been built, or will be changed.

The plant changes are an improvement in the radiation *monitoring system.

SAFETY EVALUATION An Unreviewed Safety Question is not involved in this change since it only revises the affected Tables to reflect actual plant equipment locations and functions.

The plant design change does not adversely impact containment or gas decay tank isolation capability.

TABLE 3.3-3 {Continued) ti'

):>

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION r-,.,,

3:

c MINIMUM

z TOTAL NO.

CHANNELS CHANNELS APPLICABLE

-i FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

b.

Phase "B" Isolation e

1)

Manual 2 sets of 2 l set of 2 2 sets of 2 l, 2, 3, 4 18

2)

Automatic 2

l 2

l, 2, 3, 4 13 Actuation logic

3)

Containment 4

2 3

l, 2, 3 16 Pressure--High-High w

c.

Purge and Exhaust

~

Isolation w

I

1)

Manual 2

l 2

l I 2, 3, 4 17 en

2)

Containment Atmo-3 l

2**

l I 2, 3, 4 17 sphere Radioactivity-High

4.

STEAM LINE ISOLATION e

a.

Manual l /steam line l/steam line l/operating l, 2, 3 18 steam 1 ine

b.

Automatic 2

l 2

l, 2, 3 13 Actuation logic

c.

Containment Pressure--

4 2

3 l, 2, 3 16 High-High

    • The unit vent sampling monitor may also function in this capacit~ with when the purge/pres*ure-vacuUll re11et i*olation valTes are open, 1owered setpoint~

I.,.

VI

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r-m 3::

c::

z

>-4

-I N

w w

I....

co TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO.

FUNCTIONAL UNIT OF CHANNELS

b.

Phase 118 11 Isolation

1)

Manual 2 sets of 2

2)

Automatic 2

Actuation Logic

3)

Containment 4

Pressure--High-High

c.

Co~ainment Ventilation Isolation

1)

Manual 2

2)

Automatic Actuation Logic.

-2

3)

Containment Atmo-sphere Gaseous Radioactivity-High

4.

STEAM LINE ISOLATION

a.

Manual 2/steam line

b.

Automatic 2

Actuation Logic

c.

Containment Pressure--

4 High-High CHANNELS TO TRIP 1 set of 2 1

2 1

1 1

1/steam line l

2 MINIMUM CHANNELS OPERABLE 2 sets of 2 2

3 2

2 1

1/operating steam line 2

3 APPLICABLE MODES 1,2,3,4 1' 2, 3, 4 1, 2, 3 1, 2, 3, 4 1, 2, 3, 4 1, 2, 3, 4.

1, 2, 3

1. 2, 3 1' 2, 3 ACTION 18 13 16 17 13 17 21 20 16
    • ' The unit vent sampling monitor may also function in this capacit~ with lowered setpoints, when the purge/pres*ure-vacuum relief i*olatio~ valves are open.

)

  • J J

V)

TABLE 3.3-6

)>

RADIATION MONITORING INSTRUMENTATION r-l'T1 3:

c MINIMUM z

CHANNELS APPLICABLE ALARM/TRIP MEASUREMENT

-i INSTRUMENT OPERABLE MODES SETIPOINT RANGE ACTION N

1.

AREA f<<>NITORS

a.

Fuel Storage Pool Area 1

~ 15 mR/hr 10~

1 - 104 mR/hr 23

2.

PROCESS MONITORS

a. Contairnent
1) Gaseous Activity l*llll a) Purge & Pressure-Vacut111 Relief

~ 4.5 x 10-2 101 - 106 CJ>ll 25 w

Isolation 1

  • 2, 3, 4 & 6

~

Ci/Sec w

b) RCS Leakage 1

101 - 106 Cpll I

3 & 4 N/A 24 w

Detection 1, 2,

'°

2) Particulate Activity -

1 RCS Leakage 1, 2, 3 & 4 N/A 101 - 106 Cpll 24 Detection

" With fuel in the storage pool or bulldtng.

L

    • The unit vent sampling monitor may also function in this capacity, with lowere~ setpoints, when the purge/pres*ur~-vacuum relief i*olation valves are open *

]

TABLE 2.3-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS

  • Smnp11ng Fi"equency Detectable Gneou1 Type of Concen1r111on1 Source and Analysis Activicy Antilyli1

~C1/m11*

A. W1Ste Gas Decay Tank Releases Each Tank to Principal Gamm-a Emitters 10_...

be Released H-3 10-*

I. Containment Purge Releases Each Purgee Principal GimimJ Emitters 1Q-4C H-3 10-*

C. Condenser Air Ejector Monthly Principal Gamma Emitters\\.

1tr' c H-3 10-*

D. Environmo:ntal Release Points Monthly Principal Gamma E mittcrs 10-4 ti, c (Gar. Samples)

H*3 10-*

Weekly (Ch;:rcoal Sample) 1*131 10-ll

  • Monthly (Charcoal Sample) 1*133, 1-135 Hr10 Weekly (Particulates)d Princi~I Gamma Emitters (Bl-La-140, I-~31 and others) 10-*I Monthly Compos.itcd (Particulates)

Grosse

  • 10-11 Quarterly Composited Sr-89, Sr-90 10-11 CPart.icu!i tes.1
  • The above detectability limits for activity analysis 1re based on technical fe11ibility and on the potential significance in the environment of the quantities released. For some nuclides. lower detection limits may be readily achievable, and when nuclides are 1T1Casured below the stated limits, they should also be reported.
  • For certain mixtures of gamma emitters, it may not be possible to measure r.ctionuclidcs at levels near their sensitiv-ity limits when other nuclides arc present in the sample at much higher levels. Under these circummmces, it will be more appropriate to calculate the levels of such radionuclides using observed ratios with those radionuclidcs wluch are measurable.

c Analyses shall also be performed following t!ach refueling, startup, or similar operational occurrence which could alter the mixture of radionuclides.

  • To be representative of the aversge quantities and mnc:entration1 of r~ioactive material\\ in particulate form released 9 pseous effluents. 11mptes should be mlleeled in proportton ao the rate of flow o' the effluent nrum.
  • Bot applicable to Pre11ure-Vacuua Belief operation*
2. 3-21

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I TABLE 2.3-4 SALE" STATl<Jt WEOOS WASTE SYSTOt LOCATION! OF PROCESS ANO EFFLUENT MOl\\!ITORS /\\ND SAivlrLEP.S REQUIRED BY TECHNICAL SPECIFICATIONS Conttnuous Grab MtMU~,..!t't bdhtton Auto Co1111ol 10 s.1mple Pr0ttn Sl~om or Rtit.ne Pol"'

A111111 holat:on \\'alvl!

"°nttor Sl;ihun Not.le Gas I

Particullle H-J

.Alpha Viste Gas Oeuy T1nlts x

x x

x x

Condenser Atr Reinoval Syst*

x x

x

  • X x

x x

Pllnt Vent x

lb x

x x

x x

Building Ventilation Systtmg Re1ctor Containment Bulldlng Cwhenner xd t!l~re is liowt x

x x

x x

x x

N.

Auxiliary Building and 111*11te Are11 IC

~

t>Ft~

x

)(

)(

x Fuel Handling 8i Star1911Bui1dlng8 IC x

x

)(

x

""' \\

  • ~\\,\\.().

p<.Jre-6 p..-<1i pr

/

~E-

~

pF>6t vl' l)t>'f'~

0

,..,._,1

~

Turbine Gland Stal Conde *

.~

le

)(

x

)(

x Waste Gas Dtsch1rt1 Ltne x

)(

x Sl*ce*theH Jl'OHH et.I'._ n liulLtt111... tUatloll *J9t-. are rout.. to tba pl.lat *at, the... roe* cntt..-o -.it* at tba Wlrlhal tie-ch*r1e point to th*.. ta Allha1111t duct le ellalaated. Oae contlauOUll moaltor at the final rellJlae polat le euff lclomt

  • x x

x x

x

)(

x

  • Contlnuou*lJ.aaltored. Aleo Include* coatlnuoue todl..-, aoble 189 aad pertlculat* 110nltor1 which are In **rYlce durta1 vaete 1** decaf t.. k rel*....

end cont*ln11ent purgln1 oper*tlone.

c Cr*b *..,1. etetlo.. frcm wt.le~ llOftthly... *ample* (Table Z.)-1) ere to be t***a. Aleo, 1reb 1.-plee *hould b* token *nll *eaeurad to det~~..ine the.

procee* 1trem1 or buildiJl<< *entill*tlon *J*tem *ource whene*er *a un*irpl*ined Iner**** l* lndlc~ted bf th* pleat **nt eaipler-.oaltor**.

Include* contl11UOU8 80bl* 1a* aJaltor.iblch 1M111ltor1 thl* loc*tlD111 *t all ti... otlaer th*a ve*t* decaf tank reta.. 01 111111 cC111t1t.. eat pur11A1 oper*tlom9.

N * 'f' N w TABLE 2.3-4 SALOt STATU*

WEOOS WASTE SYSTEM LOCATION OF PROCESS ANO EFFLUENT MO~nons /\\i\\10 SAivlrLERS REQUIRED BV TECHNICAL SPECIFICATIONS Rldtatton Continuous Grab Auto C111111ol 10 S.Jm11le

,,_.. Strtlrft °' Rm.. ll'oinl A11nt holallon \\'ohrt' Monitor Sl.Jl1un NoLla Ga1 I

Partiaila91 IHte C.s Dlc:IJ TIMI x

x x

x c.t*ns*r Afr a...11 S11t*

x x

x

  • X x

x Plut Yent

>C

)(

x x

x x

Caatabmut Purve/PnHure - Yecuum.. u.r x

x x

x Bullding Ven1ll11fon Systems Auxllltry BuHdlng... b6fl1te ha1 IC x

x x

Fuel Hlftdlfnt

  • Stor191 le,,lldlnf IC x

x x

Turbine Gland Seil eon.nw 1 IC x

x x

~

H*3 Alpfle x

x x. x x

x x

x x

x x

x x

x a lbee 0dleN fr9a.. HW._ W.. IUI.. ftatllat....,.t_ are irwt.. te tllil plMt,,_te tllil Mllll fer a Pllt.........tt* at tM... tYIMJ. ae-da.r1e point to the.... ahadt "9ct I* el.. laot... One coat!.. -

-ltor at die Uaal. rel.. H polat 1.e eufllcl*t*

Autceiatically ieolat** waate Ga* Diacharge Line on HIGH RADIATION aignal from Gaaeoua Monitor, R41C. Thi* monitor (R41C) along vith R41A and a41B

]

vill initiate iaolation of Contaill1ml8nt Purge/Preaaure-vacuWll Relief Syate11 on HIGH RAD~ATJON also.

e Cra* *-.le *tAltleM h*.. le* MlltlllJ pa __,1.. (T*He 2.~2) ere to** te.... AIMe 1ra* euplu.......... t... a............ to dete~"alM die*

proc*** atr*.. or bulldlaa... ttlattoe *F*t.. aource... *n***r *a...... lelaed Iner**.. le l... lcat..t *1 tbe pl.. t ***t.... ler-.onltere *.

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