ML20206K286

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Amend 10 to License DPR-35,deleting Tech Spec Pages 179 & 191A & Adding New Pages 179,179A,179B,191A & 191B Re Airborne Effluent Release Limits
ML20206K286
Person / Time
Site: Pilgrim, 05000000
Issue date: 05/23/1975
From: Ziemann D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20204E974 List:
References
FOIA-86-58 NUDOCS 8606300063
Download: ML20206K286 (9)
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UNITED STATES NUCLEAR REGULATORY COMMISSION ,

W ASHINGToN. D. C. 20S55 BOSTON EDISON COMPANY C9CKET NO. E0-293 PILCRD1 N11 CLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 10 License No. DPR-35

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

A. The application for amendment by Boston Edison Company (the licensee) dated April 2, 1975, as modified by letter dated May 22, 1975, 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 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 conducted in compliance with- the Commission's regulations; and D. The issuanc- of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

2. Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Facility License No. DPR-35 is hereby amended to read as follows:

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" B. Technical Specifications ,

The Technical Specifications contained in Appendices ~ -

A and B, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No. 12."

3. This license amendment is effective as of May 23, 1975.

FOR Tile NUCLEAR REGULATORY COMISSION

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Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Reactor Licensing

Attachment:

Change No. 12 to the Technical Spbeifications .

Date of Issuance: May 23, 1975 i

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f ATTACENENT TO LICENSE AMENDMENT NO.10 i

CHANGE NO. 12 TO THE TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 i

Delete pages 179 and 191A. Add the new pages numbered 179, 179A, 1798, l

191A and 191B. The revised pages have marginal lines indicating whe're the changes appear.

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LIMITING CO';DITIONS FOR OPEMTION SIPVEII.?>.NCE FIGUIREMI'CS 3.8.B Airborne Ef flue:nts 4.8.B Airborne Efficents

1. The release rate of grons 1. The groso and particciate act ivity except for.halegens activity of all gascous and particulatea with hali- vastes released to the environ-liven longer than eight days, cent chall be conitored and shall not e.5c ced : recorded:

Qs Qv a. For effluent strcans having

+ [2 1 continuous nonitoring capability, the activity and 0.25/E s 0.10/Ey flow rate sh ll be =or.itored and recorded, wher e: .

b. For effluent streams without Qs = relerse rate from cain continuous nonit oring capa-stack in Curico/second. bility, the. activity and rolcase volume 1. hall bc Qv = release rate from the conitored and recorded and reactor building exhaunt the release rate r.hsll be vent in Curica/cecond. controlled to within the limita specified in 3.S.B.1.

E = average energy per dio-integration (Mev/ dis) in the stack (c) and vent (v) effluent.

2. (a) The release rate limit of 2. Gross radioactivity of coacous all radioiodines and effluents shall bc monitored radioactive materials in and recorded to ena51c release particulate form with rates of gross radioactivity half-lives greater than to be determined on an hourly eight days, released to basis.

the environs as part of the gaseous wastes from .

the site shall be such that:

5 12 1.8 x 10 Q + 1.8 x 10 Q3 <1 where:

Qy = release rate from the reactor building exhaust vent in curies /sec.

Qg = release rate from the main stack in curies /sec. 179

. LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4

3.8.B Airborne Effluents (Cont'd) 4.8.B Airborne Effluents (Cont'd) f (b) The average release rate per  ;

I site of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter 8 shall be such that: ,

5 13[1.8 x 10 Q + 1.8 x 10 Q]<1 S l l (c) The average release rate per I

site of all radiciodines and radioactive materials in particulate form with half-lives greater than eight days during any period of 12 consecutive months shall be such that:

25[1.8 x 10 Qy + 1.8 x 10 gQ]11 (d) The amount of iodine-131 released during any calendar quarter shall not exceed 2 Ci/ reactor.

(e) The amount of iodine-131 released during any period of 12 consecu-12 tive months shall not exceed 4 Ci/ reactor.

(f) Should any of the conditions of 3.8.B.2(f)(1) or (2) listed below exist, the licensee shall make an investigation to identify the causes of the release rates, define and initiate a program of action to reduce the release rates to the design objective levels. The design objectives stipulate that the annual total quantity of all radiciodines and radioactive material in particulate forms with half-lives greater than eight days, above background, from all reactors at a site should not result in an annual dose to any organ of an individual in '

an unrestricted area from all pathways of exposure in excess of 15 mrem, and that the annual total quantity of iodine-131 discharged from each reactor at a site should not exceed 1 Ci. The licensee shall report these actions to the NRC within i 30 days from the end of the quarterduringwhichthereleases:i 179A occurred. I

, , ,.. LIMITING CONDITIONS FOR OPERATIOM SURVEILLANCE REQUIREMENTS 3.8.B Airbovae Effluents (Cont'd) 4.8.B Airborne Effluents (Cont'd)

(b) The average release rate per j site of all radiciodines and -

radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter 8 shall be such that: ,

4 13[1.8 x 10 Qy + 1.8 x 10 gQ]11 l (c) The average release rate per site of all radioiodines and radioactive materials in particulate form with half- '

lives greater than eight days during any period of 12 i consecutive months shall be such that:

5 4 25[1.8 x 10 Q y + 1.8 x 10 gQ]11 1

(d) The amount of iodine-131 released during any calendar quarter shall not exceed 2 Ci/ reactor.

(e) The amount of iodine-131 released during any period of 12 consecu-12 tive months shall not exceed ,

4 Ci/ reactor.

(f) Should any of the conditions of 3.8.B.2(f)(1) or (2) listed below exist, the licensee shall make an investigation to identify ,

the causes of the release rates, define and initiate a program of action to reduce the release rates to the design objective levels. The design objectives

stipulate that the annual total quantity of all radioiodines and radioactive material in particulate forms with half-lives greater than eight days, above background, from all '

reactors at a site should not 4

result in an annual dose to any organ of an individual in' l

an unrestricted area from all '

pathways of exposure in excess of 15 mrem, and that the annual-total quantity of iodine-131 discharged from each reactor '

at a site should not exceed 1 Ci. The licensee shall report these actions to the NRC within 30 days from the end of the quarter during which the releases! 179A 3

occurred. I

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' , -- .i;* LIMITING CONDITIONS FOR' OPERATION SURVEILLANCE REQUIREMENTS 3.8.B Airborne Effluents (Cont'd) 4.8.B Airborne Effluents (Cont'd)

(1) If the average release rate per site of all radioiodines and radio-active materials in particulate form with half-lives greater than eight days during 12 any calendar quarter is such that:

50[1.8 x 10 Qy + 1.8 x 10 Qg ] >;l ,

(2) If the amount of iodine-131 released during any calendar quarter is greater than 0.5 Ci/ reactor

3. The release rate of cross gaseous 3. An isotopic analyais shall be activity from the main stack shall cade of a represeatntjve say, pig not exceed 0.10 curies /second of the scoecus radioactivity when averased ovar any calendar being releasec which shall '

q uar ter. identify and determine the quantity of the principal radio-

  • .nuclidea, except tritium, released:

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BASES:

3.8.B and 4.8.E Airborne Effleents Radioactive gacea are routinely dincharged from the station via the main

' stack and potentially f ron the building cr.h:.ust vent. The liv. ins in Specification 3.8.S are derived to keep tha off-site dauas as io e ac practicable and below the 11nito given it.10 CFR 20. 'ih e s e s p e ' i f .' c ., t .'. c e apply to the interim period prior to operatien of the augmented geseous holdup system; 43 sen appropriate changes vill be ende to the npccificatio n.

Detailed dose calculations have been made by the applicant and are contained in Appendix E of the F5AR. These calculations cor. sider site meteorology and isotopic content of the effluent. Independent oc9a cal-culationa for neveral locations off-site have beca made by thr: AZC craff.

The AEC ctaf f method utilized on-site netcorological data deve cped by t 6.e applicant.

The nethad utilized by the staff is described in $2ction 7-5.2.3 of *

"Metcotology and Atomic Energy-1968". The resulco of these ca.-93atin.;

were rr.nre conservative than those generated by the applicant t.nd vere thus chosen to be used as the baala of establir,beent of the It .re .

The equation given in Specification 3.8.B.1 provides a cethod :c t t used in au=ing the airborna effluenta frca the nnin r. tack and the mildin;;

exhaust vent that will essure that total off-site doses are not 11 excess of the limito specified in 10 CFR 20. The continuoua release of radio-active noble gaocs in airborne effluento ct the rates pernissible by Specification 3.8.E.1 are calculsted by the Cotainsion's staff to correspond to an upper linit dose of 503 nreu per year at the cost restrictive innd b6undary (S'J of the ntation) . The permissibla: release rate from the plant steck alone by thic specification is about 0.36 curies /sec bared on en average disintegration enargy of 0.7 Mev.

The application of the average' disintegration energy for the released radioactive gases makes the formula appropriate to a vide range of release 4 conditions and extend 2d holdup periods.

! The release rate Specifications for a radioiodine.and radioactive material i in particulate form with half-lives greater than eight days are dependent on existing radionuclide pathways to man. The pathways which were examined

' for these Specifications are: 1) individual inhalation of airborne i radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, and 3) deposition onto grassy areas where milch animals graze with consumption of the milk by man. Methods for estimating doses to the thyroid via these pathways are described in Draft Regulatory Guide 1.AA. The offsite location with the highest anti-l cipated thyroid dose rate from radioiodines and radioactive material in 12 Particulate form with half-lives greater than eight days was determined I using on-site meteorological data and the expressions described in Draft

{ Regulatory Guide 1.AA.

i Specification 3.8.B.2(a) limits the release rate of radiciodines and l radioactive material in particulate form with half-lives greater than eight days so that the corresponding annual thyroid dose via the most restrictive pathway is less than 1500 mren.

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BASES:

i 3.8.B and 4.8.B Airborne Effluents (Cont'd) 4 For radiolodines and radioactive material in particulate form with half-lives greater than eight days, the most restrictive location is adairyc9wlocaged5600metersinthewgstdirgetion(ventX/Q=

, 2.2 x 10 sec/m ; stack X/Q = 1.8 x 10 sec/m ).

Specification 3.8.B.2(b), (c), (d) and (e) establishes upper offsite i

levels for the releases of radioicdines and radioactive material in particulate form with half-lives greater than eight days at twice the 12 design objective annual quantity during any calendar quarter, or four

{ times the design objective annual quantity during any period of 12 consecutive months. In addition to the limiting conditions for operation of Specifications 3.8.B.2(a) through (e) the reporting requirements of 3.8.B.2(f) provide that the cause shall be identified

, whenever the release of gaseous effluents exceeds one-half the design j objective annual quantity during any calendar quarter and that the proposed program of action to reduce such release rates to the design objectives shall be described.

Specirication 3.8.B.3 establishes as low as practicable limits for the relense

] levels of gaseous effluents fcr the interim period. The values chesen are consistent with intarin limits used for eth~r b W e without J aug ented systens. Under tb se ::p.:cific;. tic , the licensee vill i be requi: ed to n hc m'ch rat '.w iv.'; ': i-M.cf r.;; c'.c;ien p 3r ,

i or other appropriate nuasure., na : cay be ..:se. .cy ra heep the avera;;e radioactive ga ;cou2 1:lecca bc'c., this 1cul, but afimd:c' the flexibility rega: ding thort-teca pisnt c,wrcticn to reint in st.d. ion powcr for public t.ledo.

a Specification 3.8.B.6 require 3 t.ha t the primry conte:r s:at utnosphere i receive trectraent f or the ri caval of gr. 90:.n iolines end particul;;te i prior to ite release whenevac tha rer.c t or j a, in thz .C.'.;cda. Thh 4

specification providea n furth.c reduct!oa fre;. thic ecuccc of reloce of lodlacs and particulate 3 from the cretion,

, The tourveillar.cc requiremanto a,iv.:n und-r Sp :cificatier 4 8.L provide l an.surance thet radioactive gnaeaua efflutnto irca ti u t..':10n nrc y t oparly controlled and conttored over the life of the rtstion. tnese curveillance requirenenta ;rovide the darc fer the 11 & nnue t.nd the Car =icsion to l cvaluate the statien's performance relctive to re.dienctiva gaaceca var.tes releancd to the envisoar.ent. Reports ca the qu:ntities of radioactive

, materials released in gasecun effluentu shall be furniched to the Con- .

j mission on the bnuf s of Section 6.6 of the.e Technical _ Specifications.

On the basis of auch reports and any additicnal intornation the Cor ris-i slon nay obtain from the licensee or othera, t'he Cornission r.ry from time
to tin.e require the licensee to take auch action ca the Commission deems

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appropriate.

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