ML20027C874

Amends 48 & 13 to Licenses DPR-70 & DPR-75,respectively, Revising Process & Effluent Monitors to Agree W/Existing Plant Conditions

ML20027C874
Person / Time
Site:	Salem
Issue date:	10/18/1982
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20027C875	List: ML20027C874 ML20027C877 ML20027C878
References
NUDOCS 8210270355
Download: ML20027C874 (14)

Text

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g NUCLEAR REGULATORY COMMISSION w AsmNGTON, D. C. 20555 r,

PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY

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ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272

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SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-70 l.

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

A.

The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and 5

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Light Company and Atlantic City Electric Company (the licensees) dated August 10, 1981 and modified by letter dated June 22, 1982, 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; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commtssion; 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 amendme;t will not be inimical to the common defense and security or to tM health and safety of the public; and E.

The issuance of this amend.nent is in accordance with 10 CFR Part 51 of the Commission's req; elations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the at'tachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-70 is hereby amended to read as follows:

(2) Technical Scecifications The Technical 5pecifications contained in Appendices A and B, as revised through Amendment No. 48, 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.

THE NUC R EGULATORY COMMISSION l

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.even Operating Reactors a ch #1 Division of Licensin I

Attachment:

Changes to the Technical Specifications Date of Issuance: Oct'ober 18, 1982 I

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,L.3f ATTACHMENT TO LICENSE AMENDMENT NO.48 I~

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FACILITY OPERATING LICENSE NO. OPR-70 DOCKET NO. 50-272 M

91 Revise Appendix A as follows:

o 3

Remove Pages Insert Pages a

O; 3/4 3-18 3/4 3-18 f,

3/4 3-36 3/4 3-36 y

Revise Appendix B as follows:

Remove Pages Insert Pages

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2.3-21 2.3-21 2.3-23 2.3-23 I

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r TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION N,,

,s MINIMUM c

APPLICABLE 2.1 TOTAL NO.

CHANNELS CHANNELS

_ FUNCTIONAL UNI._T.

OF CilANNELS TO TRIP OPERABLE MODES ACTION H

b.

Phase "B" Isolation f-1)

Manual 2 sets of 2 I set of 2 2 sets of 2 1, 2. 3. 4 18 2)

Automa tic 2

1 2

1.2.3.4 13 Actuation logic 3)

Containment 4

2 3

1.2,3 16 Pressure--liigh-High 1

t' c.

Purge and Exhaust Isolation 5

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Manual 2

1 2

1.2.3.4 17 m

2)

Containment Atmo-3 1

2**

1. 2. 3. 4 17 sphere Radioactivity-High c.

4.

STEAM LINE ISOLATION

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Manual 1/ steam line 1/ steam line 1/ operating

1. 2. 3,

1R g-steam line S,

b.

Automatic 2

1 2

1.2.3 13 Actuation Logic 2

c.

Containment Pressure--

4 2

3 1, 2. 3 16 e

liigh-Higte ee The unit vent sampling moottor may also faaetica la this capacity,with lowerea setPotate, when the purse /preneure-vaamaa relief teolation valves are opea.

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TABLE 3.3-6 RADIATION MONITORING INSTRlMENTATION U

p, MINIMlM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES

_SETPOINT RANGE ACTION Ep 1.,

AREA MONITORS 1 15 mR/hr 10-I - 10 mR/hr 19 4

a.

Fuel Storage Pool Area 1

2.

PROCESS MONITORS 4

a.

Containment

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1) Gaseous Activity if a) Purge & Pressure-F Vacuum Relief.

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Isolation 1.2.3.4&6 1 2 x background

10) - 106 cpm 22 2

b) RCS Leakage 1

6 Detection

1. 2. 3 & 4 N/A 10 - 10 cpm 20 u.

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2) Air Particulate Activity if a) Purge & Pressure-

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Vacuum Relief 1

6 Isolation 1.2.3.416 1 2 x background 10 - 10 cpm 22 b) RCS Leakage 1

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Detection

1. 2. 3 & 4 N/A 10 - 10 cpm 20 k

3)

Fixed Filter lodine-E Purge & Pressure -

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Vacuum Relief

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A isolation 1#

1. 2. 3. $ 8 6 1 2 x background 10 - 10 cpm 22 L

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• With fuel in the storage pool or building.

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The unit vest sampling moattor may also function in this capaelts with lowerea setpointg when the purge / pressure-recusa relief teolation valves are open.

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E; TABLE 2.3-2 q

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RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS c

i' on,c,w, M11 Frequency 9,,

y' seiseve and alysis 4,i,6,, a sy,*

Ince/mg*

senses 1

h A. Weste Gas Decay Tank Releases Each Tank to Principal Gamma Emitters 10"**

'5; he lleleased Y

H.3 10-*

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3. Containment Purge Releases Each Purge Principal Gamma Emitters 10-*'

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8 3

H3

'10-*

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pj C. Condenser Air Elector Monthly Principal Gamma Ernitters 10"*g e q

l H3 10-*

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D. Environmental Release Poin.ts Monthly Principal Gamma Emitters 10-*t. e (Gas Samples)

H.3 10-*

.l 10-'8 Weekly (Ch:rcoal Sampic) 1131 Monthly (Charcoal Sample) 1133.1135 10**

.i-g Weekly (Particulates)d Principal Gamma Emitters

.d (Sa-La-140,1-1,31 and others) jgH 8 Monthly Composite *

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Facticulates) 10" '

l.

Gross o l

10-'8 l'

Ovarterly Composite

• Sr-49. Sr-to Farticulates) aThe above detectability limi s for activity analysis are based on technical feasibility and on the potential significance in the environment of the quantities released. For some nucfides, lower detection limits may be readily achievable, and when nuclides are measured below the stated limits, they should also be reported.

"For certain mixtures of gamma emitters, it may not be possible to maesure radionuclides at levets near their wesitiv-Ity limits when cther nuclides are present in the sample at much higher levels. Under these circurnstances.it will be more appropriate to calculate the levels of such radionuclides using observed ratios with those radionuclides which are encesurable.

' Analyses shall also be performed following each refueling, startup, or similar operational occurrence which could alter the mixture of radionuclides.

• To be representative of the everage avantities and concentrations of radioactive materials in particulate foem released h gaseous effluents, semp8es shovid be collected in proportaon to the rate of flow of the effluent stream.

S Not applicable to Pressure-Yaessa Relief operations SALEM CNIT 1 2.3-21 Amendment No. 48 l

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satin stArles sAsteus unsTE sisiot t.OCATION OF PROCESS AND EFFLUENT MONITOI13 AND S A;.trLER5 REQUIRED BY TECHNICAL. SPECIFICATIONS Gesh neaIeteen A.i. ca..ee i.

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so.se p=em swee,in ee peeeeee eeast Alere 8eelas.ea ve e M* alt #r s

seas.ea 8deine Ces g

restem.8ees M3 Alphe lanste Gas Dooy fanns X

X X

X X

X Ceedenter Alr assovel system X

X X

-X X

X X.

X Fleet veet X

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X X

X X

X X

X castelemmet purwe/preseere - vacuus neuer X

X X

X X

X r

Suildias Ventitessen Sycems e

C e4 Ammitlery Svilding and Reeeeste Aros 3

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g g

g Y

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Fuel Handing & Storage Sullding" E

X X

X X

X Twbene Glend Seel Condenser

• I" X

X X

X X

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stese Wee procees etresse er bestates ventilasten eyesene se's rested to the pleet verste the need for a emettaesse esatter et the la~adtgedenE dae.

I' shuse roles to N este enhavet Act le olteleeted. One senatessee eestter et the taeel relo ee potes se entstesset.

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Automatically teolates toeste ces Discharge Line se NIGN RADIAT!0ef signal trem Caseous stoeltor. 341C. This opetter feelC) along trith 341A and 3433 trt!! !aittete teolettom of Costeineent Purge /Fressure-Vecoue sallef Systaan ce NICM RAD (ATJ001 also.

4 CJah esople etestene free obteh meetkly see semples (Yeble 3.)-2) are to be tones. Aloe. greb eemples abeeld be takes and seneered se deteimies the

• peacees etream er butIdtng veestlettee orates esures ebenever se seeepletoed leeresee to tedicated by the pleet vest peopter-eastters.,

I SALEtt UNIT 1 Amendment No. 48 i.

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!jgr 3\\'g UNITED STATES NUCLEAR REGULATORY COMMISSION

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/ j WASHINGTON. D. C. 20555 2.','.. '

i PUBLIC SERVICE ELECTRIC AND GAS COMPANY il PHILADELPHIA ELECTRIC COMPANY

'J DELMARVA POWER AND LIGHT COMPANY j

ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 j.f AMENDMENT TO FACILITY OPERATING LICENSE O

en No bPR-75 1.

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

A.

The application for amendment by Public Service Electric and

~ l Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated August 10, 1981 and modified by letter cated June 22, 1982 complies with the standards and requirements of the Atomic 3

Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set fortfi in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 f

conducted in compliance with the Commission's regulations; 5

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 y

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.

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Accordingly, the license is amended by' changes to the Technical Specifications as indicated in the attachment to this license

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amendment, and paragraph 2.C.(2) of Facility Operating License F

j No. OPR-75 is hereby amended to read as follows:

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(2) Technical Soecifications J

h The Technical Specifications contained in Appendices

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A and B, as revised through Amendment No.13, are hereby incorporated in the license. The licensee shall q

operate the facility in accordance with the Technical Specifications.

I 3.

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

F R THE NUCLEAR REGULATORY CCMMISSION 1

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'l3 r fi f Operating Reacto s Br nch #1 Division of Lice

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Attachment:

Changes to the Technical Specifications Date of Issuance: October 18, 1982 i.;

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O ATTACHMENT TO LICENSE AMENDMENT NO.13

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FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:

Remove Pages Insert Pages rn V

?

3/4 3-18 3/4 3-18 e

3/4 3-39 3/4 3-39

'l Revise Appendix B as follows:

Remove Pages Insert Pages

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5 2.3-21 2.3-21 2.3-23 2.3-23 s

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. t TABLE 3.3-3 (Continued) v.

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!E ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION e

c 5

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO IRIP OPERABLE MODES ACTION b.

Phase "B" Isolation I)

Manual 2 sets of 2 I set of 2 2 sets of 2 1,2,3,4 18 i '.

2)

Automatic 2

1 2

1,2,3,4 13

~'

Actuation Logic L*

3)

Containment 4

2 3

1,2,3 16 h

Pressure--High-High p

)

w c.

Containment Ventilation

..{'

D Isolation 1)

Manual 2

1 2

1,2,3,4 17 b

E-2)

Automatic Actuation Logic 2

1 2

1,2,3,4 13 e

)

0**

1 1

1,2,3,4 17 3)

Containment Atmo-sphere Gaseous Radioactivity-High i

F 4.

STEAM LINE ISOLATION m

h a.

Manual 2/ steam line 1/ steam line 1/ operating 1, 2, 3 21 steam line l

3 b.

Automatic 2

1 2

1,2,3 20 I

2 l

Actuation Logic O

c.

Containment Pressure--

4 2

3 1, 2, 3 16 High-High p;

The untt vent sampling monitor may also function in this capacity,with lowered setpoints, when the purge / pressure-vacuum relief isolation valves are open.

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TABLE 3.3-6

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m5' RA01ATION MONITORING INSTRUMENTATION

~

g MINIMUM

- Jl f5 CilANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION

};

1.

AREA MONITORS I'

-1 4

inelStoragePoolArea 1

S 15 mR/hr 10

- 10 mR/hr 23 i:

a.

2.

PROCESS MONITORS

~

a.

Containment c

1) Gaseous Activity

• 0 a) Purge & Pressure-1**

,i.

Vacuum Relief.

-2 t

Isolation 1, 2, 3, 4 & 6 5 4.5 x 10 10I - 100

.p cpm 25 C1/Sec

. ! i.

Y b) RCS Leakage 1

M Oetection 1, 2, 3 & 4 N/A 101 - 106 24 cys y

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2) Particulate Activity - 1 ir RCS Leakage Detection 1, 2, 3 & 4 N/A 101 - 106 it cpm 24 i

E h

k

= With fuel in the storage pool or building.

R S

• • The unit vent sampling monitor may also function in this capacity,with lowered setpoints, S

when the purge / pressure-vacuum relief isolation valves are open.

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RADIDACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS h

sa iia r m a aci 1,

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.A"',;;,,s andgalysts A,si,i,y An.syg, gacumq*

gewse 4,

A. Waste Gas Decay Tank Meleases Each Tank to Principal Gamma Emitters 10-**

be llaleased 41 H.3 10-*

3 3

8. Containment Purge Releases Each Purge Principal Gamma Emitters 10-**

8 5

H.3 10-*

C. Condenser Air Ejector Monthly Principal Gamma Emitters.

10-*

H3 10-8 D. Environmental Release Poi s Monthly Principal Gamma Emitters

'10-*

(Gas Samples) 10-'8 Weakly (Charccal Sample) 1131 4

Monthly (Charcoal Sample) 1133,1135 10-'8 Weekly (Particulates)d Principal Gamma iimitters (Ba-La-140,1-1,31 andothers) jg-i t Monthly Compositc*

(Particulates) 10-"

Gross a 10-"

Quarterly Composite

• Sr-89. Sr-90 l

(Parsiculates)

• The above detectability limi s for activity analysis are based on technical feasibility and on the potential significance in the environment of the quant.ities released. For some nucfides. lower detection limits may be readily achievable, and when nuclides are measured below the stated limits, they should also be reported.

• For certain mixtures of gamma emitte-s, it may not be possible to measure radionuclides at lewis near their sensitiv-ity limits when other nuclides are present in the sample at reuch higher levels. Under thne circumstances.it will be more appropriate to calculate the lewis of such radionuclides using observed rstics with those radionuclides which are measurable.

' Analyses shall also be performed following each refueling, startup, or similar operational occurrence which could alter the mixture of radionuclides.

• To be representatin of the average cuantities and concentrations of radioactiw materiah in particulate form released h gaseous effluents, samples shot.4d be collected in proportaon to the rate of flow of the effluent stream.

4 Not applicable to Pressure-Tacuna Ielief operations 2.3-21 Amendment.No. 13 SALEM UNIT 2 s.

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.,t SALEM $1Aftest SAS(OUS ttASTY ST5ffM

' i LOCATION OF PROCESS AND EFFLUENT MONITons AND SAall'LERS REQUIRED BY TECHNICAL. SPECIFICATIONS Cesh Radletlen Auto cenises se Cantinuous 8aseesse*=ene 3,,,,,,,,

Procese Streene et fleisees relat Alasu 88*:a***a Va'ee M*I I 8 f 583'a=*e Neide C**

a raresci.seie 94-3 Alphe ianste ses pecar Tests X

X X

X X

X Condenser Air aseevel System X

X X

X X

X X

X Plaat vent X

/

X X

X X

X X

X 4

on.telee.et terw /rreesere - veceum netter X

X X

X X

X i

8vil6ag VenilleiBen Systems i

e I

t

,ro Avalliwy Be,48 ding and Redenste Aros g

X X

X X

X Y

8 Fuel Hanssling & Starage Building" 3

X X

X X

X rw t.s I

e C

h Tvrt:ine Glend Seal Cendreser

• 3 x

x x

x x

8 5

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8 ss ee the.e p.ec.ee eermeee w bestases ve salaisse eyesame are e.eaea to the ptees vesse the need rer a seesteesee meester oc the seatetaset ase-l ehuse eenet t. sw..es. enheest east se.nn.nestea. one seessene.e ente.t et the ramen e.neseo p. net se sortgesene.

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,esto.eticelle toolates tenete See Discharge Line on NIGN RADIATICII algast from Geseoese peonttor 341C. This mentter 1a41C) along trith 2414 ene R41e

.trl!! inttiste teolatir.,n of Conte!n.ent targe/Fressure-vacieu. Bellet systess on NIGII RADLATJ0st eleo.

8 Crab eseple etettees free e6 ten monthly see eseples (Table 3. F2) are to be.tebee. Alees greb semples ebeeld be tekee med messered to desessJee she' psecese essene er butIdlag ventilettee eretse eeurce ehe.ever se seempleleos 8.crosee le Indiested by the yleet weet sesqyles-emetters..

SALEM UNIT 2 Amendment No. 13 i

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