ML20054D616

Amend 57 to License DPR-35,changing Reporting Requirements for Radiological Environ Surveillance Program Data & Changing Table of Containment Isolation Valves

ML20054D616
Person / Time
Site:	Pilgrim
Issue date:	03/20/1982
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Boston Edison Co
Shared Package
ML20054D617	List: ML20054D616 ML20054D621
References
DPR-35-A-057 NUDOCS 8204230199
Download: ML20054D616 (9)

Text

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NUCLEAR REGULATORY COMMISSION

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WASHING TON. D. C. 20555 BOSTON EDISON COMPANY DOCKET NO. 50-293 PILG' TIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.57 License No. OPR-35 1.

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

A.

The application for amendment by the Boston Edison Company (the licensee) dated February 23, 1932 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission'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 regulatient of the Commission; C.

There is reasonable assurance (i) that the activities authorized by tnis 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 Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. OPR-35 is hereby amended to read as follows:

8.

Technical Saecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.57, are hereby incorporated in the license. The ifcensee shall operate the facility in accordance with the Technical Specifications.

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3.

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

4 FOR THE NUCLEAR REGULATORY COMMISSION f.,.dPra'AA b

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Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 20, 1982 2

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ATTACHMENT TO LICENSE-AMENDMENT NO. 57 FACILITY OPERATING LICENSE NO. DPR,

DOCKET N0. 50-293 1

i Replace the following pages of the Appendix "A" Technical. Specifications with the enclosed pages. The revised pages are identified by amendment 4

number and contain vertical lines indicating the area of change.

Remove Insert i

109' 109 158C

'158C 162 162 223 223 223a j

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I,1VITINO CONDIT10N tw uruuuiv.i 3 5.D Raaetor Core f:cistion Coolinc 4.5.D Reacter Care Tselstien Ceolin-(RCIC) Subsy: ten (Cont'd)

(RCIC) Sub:y: tem (Cont'd)

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d.

Flow Rate at once/3r. cath:

1000 psig e.

71ew Pate at Cnce/c;ersting 150 psig cycle The RCIC ;u=p chall deliver p.:

1 cast LCO sp: for a sy te: head c rrespondd=4 to a reactor pres-sure of 10C0 to 150 psig i

2.

Tro: and af ter the date that the 2.

'When it is deter =ined that the RCIC RCICS is =ade or found to be inop.

subsystem is inoperable, the hPCIC erable for any reason, continued shall be de=enstrated to be operstle reacter ; ver operatien is per is.

in=ediately and veekly thereaf ter.

sible c=1y during the succeeding seven days provided that during cuch seven days the hPCIS is oper-able.

3.

If the require =ents of 3.5.D cannot be =e t, an orderly shutdown shall be initiated and the reactor pres-sure shall be reduced to or belev 104 psig vich1: 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3 5.I Aute atic repressurizatien 4.5.E Aute=atie actressurizatien System (AD3)

Systes (ADS) 1.

The Automatic Depressurization Sub-1.

Durinc each operating cycle the syste= shall be operable whenever fo11cving tests shall be performed there is irradiated fuel in the on the ADS:

reacter vessel and the reactor pres-rure is greater than 104 psig and a.

A si=21sted cute =stie crus-ic:

prior to a startup fro = a Cold Cen-test shall be perfer:ed prier to dition, except as s;ecified in startup after each remeling cut-3 5.r.2 delev.

age.

b.

With the reactor at pressure, each relief valve phall be man-ually opened until a corresponding

hange in reactor pressure or =ain turbine bypass valve pesiciens indicate that steam is flevine fr:m the valve Perform a tese from the alternate c.

A=endment No. 32' 57 shutdown panel to verify that the relief valve solenoids actuate.

Test shall be performed after each refueling outage prior to startuo.

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3.7,8 (Continued) 4.7.3 (Continued) shutdown shall be c.

At least once every 18 months initiated and the reactor the following shall be shall be in cold shutdown demonstrated:

within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and irradiated fuel handling operations shall be teminated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

(Fuel handl-ing operations in progress may be completed).

(1)

Operability of heaters d.

Fans shall operate within at rated Jower.

1,10% of 1000 cfm.

3.

Perfom an instrument functional test on the humidistate controlling the heaters.

e Amendment No. FT, Jrf 57 158C

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TAltit.3,7 1 PRIMAllY CONTA1Tik:ENT ISOIATION VAINES 9

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Ntudier of l'ower Maximum Action on Operated Valves Operating Norutl IniLiating.

_Groun Valve Identification Inboard out. board Tiice (sec. )

Posi t,. ion E

S i r',na,l_

l Feeduater check valves,

2 2

NA O

Process I

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2 Oxygen Analyzer System 16 y

0 GC i

Standby liquid control system j

check valves i

i 1

1 NA C

Process 3

Bl!RS shutdoun cooling suction isolation valves 1

1 30 C

sc I

35 RilHS shatdown cooling injection isolation valves 2

30 C

sc l

3 Reactor vessel head spray isola-3 tion valves 1

1 30 C

sc 2

IlllRS discharge isolation valves to radninste 1

1 20 C

SC j

la lilTI:s stema line isolution valvet 1

1 25 0

GC le Ill'CIS torus suc -lon isolation valves 2

30 C

sc 5

11C103 steam lj. isolation valves 1

1 20 0

GC 1'

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6 lleactor wate; t-leanup system t

h isolation val 1

1 25 0

GC 6

Iteactor water c.eanup system rettarn isolati<s valve 1

30 0

GC 2

Dryuell equipse t drain discharry isolal.$on valves 2

20 0

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C.

Unicue Reperting Recuirements 1.

Radioactive Effluent Release Report A report shall be sub=1tted to :he Com=1ssion within 60 days af:er January, 1 and July, 1 of each year specifying the quantity of'each of the principal radionuclides released to unrestrie:ed areas in liquid and gaseous effluents during the previous 6 months.

The for=a: and content of the repor: shall be in accordance vi:5 Regulatory Guide 1.21 (Revision 1) dated June, 1974 2.

Environmental Program Data a.

Annual Report. A report on the radiological environmen:al surveillance program for :he previous 12 months of operation shall be submitted to the Direc:or of :he NRC Regional Office (with a copy to the Director, Office of Nuclear Reae:or Regula:icn) as a separate document wi:hin 00 days af:er January 1 of each year. The reports shall include summaries, in:erpre:-

ations, and sta:istical evaluation of :he results of the radio-logical environmen:a1 surveillance ac:ivities for the repor:

period, including a comparisen vi:h preoperational s:udies, operational controls (as appropria:e), and previous envire-men:a1 surveillance reports, and an assessment of the observed impacts of :he plant operation on the environment. The reports shall also include the results of any land use surveys which affect the choice of sample locations. If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a preposed course of ac: ion to alleviate the problem.

Results of all radiological environmental samples shall be su=marized and tabula:ed on an annual basis. In the event :ha:

some results are no,e available within the 90-day period, :he report shall be submi:ted, noting and explaining the reasons fer the missing results. The missing data shall be submitted ss soon as possible in a supplementary report.

b.

The following event shall be the subject of a written report to the Director of the NRC Ragional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 60 days of the occur-rence of the event: measured levels of radioactivity in an environ-mental sampling medium determined to exceed the reporting level values of Table 6.9.C-1 when averaged over any calendar quarter sampling period. When more than one of the radionuclides in Table 6.9.C-1 are detected above lower limits of detection (LLD) in the sampling medium, this report shall be submitted if:

Concentration ((L, Concentration (2) 4 * *

• Jb 1.0 Limic Level (1)

Limic Level (2)

When radionuclides other than those in Table 6.9.C-1 are detected above LLD and are the result of plant effluents, this report shall be submitted if the potential annual dose :o an individual is equal to or greater than quarterly and/or yearly limits of Table 6.9.0-2.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in

,,g o the Annual Radiological Environmental Monitoring Report.

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Amendment No. g 57

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REPORTING LEVELS FOR RADIDACTIVITY CONCENTRATIONS IN ENVIR0fttENTAL SAMPLES 5

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Reporting Levels

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Water AirborneParticu} ate Fish, Mussels Milk Vegetables j

Analysis (pCi/1) or Gases (pCl/M )

(pCi/Kg, wet)

(pCi/1)

(pCi/kg, wet) p

l 11 - 3 2 x 104 3

4 Hn-54 1 x 10 3 x 10 2

4 Fe-59 4 x 10 1 x 10 3

Co-58 1 x 10 3 x 104 n

4 Co-60

.3 x 102 1 x 10 Zn-65 3 x 10 2 x 104 2

Zr-95 4 x 102 2

1-131 2

0.9 3

1 x 10 3

60 1 x 103 Cs-134 30 10 1 x 10 3

Cs-137 50 20 2 x 10 70 2 x 103 Ba-140 2 x 102 3 x 102 l

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l Table 6.9.C-2 i

k Reportable Annual Dose Consnittments i

5.

R 5

t Pattway Dose 1.imits m

y Dose to & x 11.5 prem total body / quarter I

t Individual due to Liquid Effluents 15.0 mrem to any organ / quarter Dose to N x f 3.0 mrem total body / year Individual due to Liquid Effluents i.10.0 mrem to any ocgan/ year Air Dose due to i 5.0 mrad ganana/ quarter t

Noble Gases i10.0 mrad beta / quarter U

W Air Dose Due to 110.0 urad ganana/ year r

Noble Gases f 20.0 mrad beta / year Dose to Nx

f. 7.5 mrem to any organ / quarter individual due to Radiolodines and Particulates Doss to N x f.15.0 mrem to any organ / year Individual due to Radiciodines and Particulates I

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