ML20214R168
| ML20214R168 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/19/1978 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214R167 | List: |
| References | |
| TAC-7355, NUDOCS 8706050383 | |
| Download: ML20214R168 (7) | |
Text
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UNITE D STATES t
E' NUCLEAR REGULATORY COMM!sslON g
.g WASHINGTON, D. C,20555 l
THE C0tlNECTICUT LIGHT AllD POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY WESTERN MASSACHUSETTS ELECTRIC C011PANY NORTHEAST NUCLEAR ENERGY COMPANY 4
DOCKET NO. 50-245 f1ILLSTONE HUCLEAR POWER STATION, UNIT NO. 1 AMENDf1ENT TO PROVISIONAL OPERATING LICENSE Amendment No. 50 License No. DPR-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Connecticut Light and Power Company, The Hartford Electric Light Company, Western Massachusetts Electric Company, and Northeast Nuclear Energy Company (the licensees) dated February 13, 1978, conplies with the standards-and requirenents 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; D.
The facility will operate in confontity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized i
by this amendment can be conducted without endangering the j
health and safety of the public, and (ii) that such activities
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will be conductea in compliance with the Commission's regulations; i
a 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.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Provisional License No. DPR-21 is hereby amended to read as follows:
"B.
Technical Specifications l
The Technical Specifications contained in Appendices I
A and B, as revised through Amendment No. 50, are hereby incorporated in the license. The licensees shall operate the facility in accordance with the i
Technical Specifications."
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This license amendment is effective as of the date of its issuance.
j FOR THE NUCLEAR REGULATORY COMillSSION j
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Dennis L. Zienang,/ Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications j
Date of Issuance: June 19,1978 1
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- o UNITED STATES f'
NUCLEAR REGULATORY COMMISslON n
E WASHINGTON. D. C 20555 THE CONNECTICUT LIGHT AND POWER C0liPANY f
THE HARTFORD ELECTRIC LIGHT COMPANY WESTERN MASSACHUSETTS ELECTRIC COMPAljY J
NOP.TrtEAST NUCLEAR ENERGY COMPANY f
DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE a
Amendment No. 42 License No. DPR-65 4
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Connecticut-Light and Power Company, The Hartford Electric Light Company, Western Massachusetts Electric Company, and Northeast Nuclear Energy Company (the licensees) dated February 13, 1978, 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; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of l
the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part
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51 of the Commission'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 amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2) Technical Specifications The Technica'l Specifications contained in Appendices A and B, as revised through Amendment No. 42, are hereby incorporated in the license.
The licensees shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is ef fective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
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1 a.w..m Dennis L. Ziemann hief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
4 Changes to the Technical j
Specifications Date of Issuance: June 19,1978
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ATTACHMENT TO LICENSE AMENDMENT NO. 50 TO PROVISIONAL OPERATING LICENSE NO. DPR-21, AND AMENDMENT NO. 42 TO FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NOS 50-245 AND 50-336 Replace the following pages of the Api,endix "B" Technical Specifications with the enclosed pages.
The revised page: 3re fdentified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 2.4-8 2,4-8 2,4-12 2.4-12
0 4
2.
For all radiciodine and radioactive materiala in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous wastes:
7.9 x 104 Qs + 3.04 x 106gi 1 y
E.
deleted F.
During the release of gaseous wastes from the waste gas holdup system of Unit 2, and the offgas system of Unit 1, at least one monitor in each process stream shall be operating and set to alarm and to initiate the automatic closure of a discharge valve prior to exceeding the limits specified in 2.4.2.2.D above. The operability of the automatic isolation valve shall be demonstrated quarterly for each unit.
G.
During operation of the augmented offgas system of Unit 1, if the hydrogen concentration reaches an alarm set point of 4% by volume, the concentration shall be reduced to less than 4% or the offgas l
flow through the augmented offgas retention equipment shall be terminated before the sampled mixture reaches the noble gas retention equipment.
l H.
If no stack monitor is operating, a shutdown-of Unit 1 shall be initiated and the reactor shall be in a hot shutdown condition within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
I.
The drywell of Unit 1 shall be purged through the standby gas treat-ment system at all times the primary containment integrity is required.
J.
The maximum activity to be contained in one waste gas storage tank of Unit 2 shall not exceed 16,000 curies (considered as Xe-133).
4 the noble gas in-process activity In the Unit No. 1 offgas system K.
rate shall not exceed 1.47 x 10g u Ci/sec averaged over 15 minutes as measured at the offgas monitor.
L.
If limiting conditions in 2.4.2.2. A through 2.4.2.2.K above are exceeded, plant operations shall be modified as required to restore compliance with these specifications. Prompt reporting requirements for exceeding these limiting conditions for operation are detailed in Section 5.6.2.a.(1).
DPR-21: Amendment No. 7f,, 97, 50 DPR-65: Amendment No. N, 34, 42 2.4-8 a
is 5.0 x 10 the ESE sector at a distance of 4022 caters where the A'/Q3 oct/u2 for grour.d re} cases, and 1.3 x 10~8' rec /n3 for cicvated releases.
The grass-goat-milk-child thyroid chain is controlling.
The asse=ptions used for these calculations are:
(1) onsite retcorologica) data for the cost critical 22.5 degree secter; (2) credit for building wake; and (3) a reconcentration factor of 1220 and a grazing factor of 0.5 was applied f or possible ecological chain eficcts f rera radioactive iodir.e and particulate releases where applicable.
Specifica tions 2. 4. 2. 2. D and 2. 4. 2. 2. C estab31sh upper [11mits f oi the relecscs iodinesar.dIr.rticulatesv.ithhalf-livfsgreaterthancich:
f of noble gases, twice the design cbjective anaual quant i ty during any days, and iodine-131 at calendar cuarter, or four tiEes the design objective alinual quantity durinp, The intent of this specification is to any period of 12 consecutive renths.
the.licensec the ficnibility of operation to atsure that the public permit is provided a dependatic cource of power under unusual operatin;; ccnditior.:
j vhich may temporarily result in h'igher releases t' nan the objectives.
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2.4.2.~'.b,
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In addition to the limiting c'onditions for operation of Spccification' the reporting require:cnts'of 2.4.2.2.A delineate tna:
'2.4.2,.2.C and 2.4.2.2.D.the ecuse be identified whenever the release of gnscous c one-half the de::1gn chjective annual quantity during any calendar quarter, and describe the proposc4 progro a of action to reduce such relcano ratcc to the design objectives.
. General Specification 2.4.2.2.F and 2. 4.2. 2.H are in accordance wit h Design 1
Criterion 64 of 10 C.R Part 50.
r Specifiention 2.4.2.2.I requires that the primary contair.:ent atmosphere ci for the removal of cascous iodiac and particulates Unit i rcccive treatment prior to its relcacc.
Specification 2.4.2.2.G and conitoring requircrent 2.4.2.3.G require that bydrogen concentration in the offgan system of Unit 1 shall be monitored at all ticca the recombiners are 1:1 service.
Specification 2.4. 2.2.[11:aits the caximum of f site dose above background to below the limits of 10 CP. Part '20, postulating that 'the rupture of r.
vaste gas storage tank holding the taxitum activity releases all of the contents to the at=osphere.
Specification 2.4.2.2.K limits the offsite dose, due to failure of the Unit to 5 rem whole body.
Analysis shows that No.1 augmented offgas system $ uCi/sec at 30 minutes delay, using the this offgas limit is 5.2 x 10 offgas mixture defined in GE BWR Radiation Sources Document 22A2703T. The limit stated in Specification 2.4.2.2.K is this activity rate adjusted for five minutes delay to the. location of the offgas monitor.
DPR-21: Amendment No. 25, 50 DPR-65: Amendment No. 70, 42 2.4-12