ML20002A400
| ML20002A400 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee, Yankee Rowe, Maine Yankee |
| Issue date: | 06/16/1977 |
| From: | Reid R, Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20002A397 | List: |
| References | |
| NUDOCS 8011170071 | |
| Download: ML20002A400 (14) | |
Text
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0 UNITED STATES p
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NUCLEAR REGULATORY COMMISslON
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11 WASHINGTON, D. C. 20555 o
YANKEE ATOMIC ELECTRIC COMPANY
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DOCKET N0. 50-29 YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. DPR-3 1.
The Nuclear Regulatory Comission (the Comission)'has found that:
A.
The application for amendment by Yankee Atomic Electri-Company (the licensee) dated March 9,1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Acti, and the Comission's rules arj regulations set fortF in 10 CFR Chapter I; B.
The facility will operate in conformity with the applicatVon, the provisions of the Act, and the rules and regulations of the Comission; 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 Caission's regulations; D.
The iss,ance of this amendment will not be inimical to the comor defense and security or to the balth and safety of the p blic; and E.
The i:suance of this amendment is in accor' dance with 10 CFR Part 61 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 2.
Specifications as indicated in the attachrtent to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-3 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 40, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of its issuance.
3.
F0 THE CLEAR REGULATORY COMMISSION
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A. Sc wencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical SpecificTtions Date of Issuance: June 16,1977 i
ATTACHMENT TO LICENSE AMENDMENT NO. 40 FACILITY LICENSE NO. DPR-3 h
DOCKET NO.-50-29 Revise Appendix A as follows:
Replace pages 6-27 and 6-28 with revised identically numbered pages. The revised page is identified by Amendment number and contains vertical lines indicating the' area of change.
The corresponding overleaf page is also provided to maintain document completeness.
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Unless othepwise authorized by the Commission, the licensee shall net assign protection factors in excess of those specified f.
in Table 6.12-1 in selecting and using respiratory protective equipment.
REVOCATION The specifications of Section 6.12 shall be revoked in + heir 6.12.3 entirety upon adcption of the proposed change to 10 CFR 20, Section 20.103, which wcuid make such provisions unnecessary.
6.13 HIGH RADIPION M.EA In Paragraph 20.203 " Caution signs, labels, signals, and controls".
lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) 6.13.1 each high rtdiscion area in which the intensity of radiation is 1000 mrem /hr or less Gall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requirina issuance of a Radiat. ion An individual or group of individuals permitted to enter such Work Permit.'
areas shall be crovided with one or more of the following:
A radiation nonitoring device which continucusly indicat" the a.
radiation dose rate in the area, A radiation monitoring device which continuously integrates b.
the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device ray be made af ter the dose rate level in the area have teen established an,d personnel have been made knowledgeable of the:r.
A health physics qualified individual (i.e. qualified in radiation protecticn procedures) with a radiation dose rate' monitoring device c.
who is responsiale for providing positive control over the activities
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within the ares and who will perform perir'ic radiation surveillance at the frequency specified in the R'.JP.
The surveillance frequency will t;e established by the Plant Health Physicist.
The above procedure shall also coply to each high radiation area in which the In addition, locked doors intensity of radiation is greater than 1000 mrem /hr.shall be provi be maintained under the administrative control of the shif t supervisor on duty and/or the Plant Health Physicist.
- Hecith Physics personnel shall be exempt from the R'-lP issuan
'durina the cerformnce of theit-rotection procedures for entry into high they are followinc plant radiation radiation areas.
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TABLE 6.12-1 (3E
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S' PROTECTION FACTORS FOR RESPIRATORS 8
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PROTECTI0fl FACTORS (Z)
GUIDES TO SELECTION OF EQUIPMENT
- PARTICULATES AND BUREAU OF MINES / NATIONAL INSTITUTE VAPORS AND GASES FOR OCCUPATIONAL SAFETY Arto HEALTH l
EXCEPT TRITIUM APPROVALS (*or schedule superseding for
. DESCRIPTION (7)
MODES (l)
OXIDE ( 3) equipment type listed.)
I.
AIR-PURIFYING RESPIRATORS 30 CFR Part 11 Subpart K facepiece, half-mask (4),
HP 5
Facepiece, full NP 100 30 CFR Part 11 Subpart K II. ATMOSPHERE-SUPPLYING RESPIRATOR g,
1.
Airline respirator 30 CFR Part 11 Subpart J Facepiece, half-mask CF 100 o)
Facepiece, full CF 1,000 30 CFR Part 11 Subpart J Facepiece, full D
100 30 CFR Part 11 Subpart J Facepiece, full PD 1,000 30 CFR Part 11 Subpart J Hood CF (s) 30 CFR Part 11 Subpart K Suit CF (5)
(6) 2.
Self-contained breathing apparatus (SCBA) 30 CFR Part 11 Subpart H Facepiece, full D
100 Facepiece, full PD 1,000 30 CFR Part 11 Subpart H Facepiece, full R
100 30 CFR Part 11 Subpart H III.
COMBINATION RESPIRATOR Any comLination of air-Protection factor for purifying and atmosphere-type and mode of opera-30 CFR Part 11 5ll.63(b) supplying respirator tion as listed above Amendment No. 40 r
UNITED STATES f
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NUCLEAR REGULATORY COMMISSION j
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WASHINGTON, D. C. 20665 VER?ONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE henchent No. 36 License No.
DPR-28 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The apolication for amendment by Vemont Yankee Nuclear Power Corporation (the licensee) dated March 30, 1977, comp;ies 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.
Tne facility will operate in confomity with the application, 1.he provisions of the Act, and the rules and regulations of
- he Comission; C.
There is reasonable assurance (1) 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 ir, compliance with the Comission's regulations; D.
The issuan:e of this amendment will not be inimical to the come.
defense anj security or to the health and safety of the public; and E.
The iseaance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l 2-2.
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 Facility Operating License No. DPR-28 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 36, are hereby inenrporated in the license. The licensee shall c;.arate the facility in accordance with the Technical Specifications.
3.
This license amendnent is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'h' Robert W. Reid, Chief Operating Reactors Branch f4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 16,1977 e
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4 ATTACHMENT TO L! CENSE AMENDMENT NO. 36 FACILITY OPERATING LICENSE NO. DPR-28 00CK2T NO. 50-271 Revise Appendix A Technical Specifications as.follows:
Insert Paaes Remove Paaes 202 202 202a The new page and changed areas on the revised page are'shown by marginal lines.
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VYNPS rce (3) Written procedures to assure the adequate fitting of respt..itors; and the testing of respiratory k.:rd protective equipment for operability immediately prior & u.,e.
O%d (4)
Written procedures for maintenance to assure full effetiveness of respiratory protective equipment, (h
including issuance, cleaning and decontamination, inspection, repair, and storage.
Written operational and administrative procedures for proper use of respiratory protective equipment, 17T :rl gr QN (S) including provisions for planned limitations on working times as necessitated by operational conditions.
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(6)
Bioassays and/or whole body counts of individuals (and other surveys, as appropriate) to evaluate n
7 individual exposures and to assess protection actually provided, The licensee uses equipment approved by the U.S. Pureau of Mines and under its apprentiate Approv'al forth in Table I below.
Equipment not approved under U.S. Hureau u. Mines Approval e.
Schedules as set Schedules may be used only if the licensee has evaluated the equipment and can demonstrate by testing, or summgg on the basis of reliable test 'information, that the material and performance characteristics of the least equal to those afforded by U.S. Bureau of Mines approved equipment of the same type, equipment are at as specified in Table I below.
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Unless otherwise authori:cd by the Commission, the licensee does not assign protection factors in excess f.
of those speci fied in Table I bel < w in. selecting and using respiratory protective equipment.
These specifications with respect to the provisions of Section 20.103 shall be superseeded by adoption of 3.
proposed changes to 10 CFR 20, Section 20.103, which would make this specification unnecessary.
In lieu of the " control device" or " alarm Paragraph 20.203 " Caution signs, labels, signals, and controls".
4 signal" required by paragraph 20.203(c)(2), each high radiation area in which the intensity of radiation
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is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall he controlled by requiring issuance of a Radiation Work Permit *. Any individual or group of individuals pcmitted to enter such areas shail be provided with one m.
more of the following:
in the area.
A radiation monitoring device which continuously indicates the radiation dose rate a.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms b.
when a preset integrated dose is received.
Eniry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
T 202 Amendment No. 36
VYNPS A health physics qualified individual (i.e. qualified in radiation protection ' procedures) with a radiation-dose rate monitoring device who is responsible for providing positive _ control over the c.
activities within the area and sho will perform periodic radiation surveillance at the frequency The surveillance frequency will be established by the Plant IIcalth Physicist..
specified in the RWP.
in which the intensity of radiation is The above procedure shall also apply to each high radiation area-In addition, locked doors shall be provided to preve greater than 1000 mrem /hr.
such areas and the keys shall be maintained under the. administrative control of the Shift Supervisor on duty and/or the Plant IIcalth Physicist.
from the RNP issuance requirement during the -performance of their
- Health Physics personnel shall be exempt assigned radiation protection duties, providing' they are following plant radiation protection procedures for entry into high radiation areas.
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UNITED STATES NUCLEAR REGULATORY COMMISSION y'
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DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Arrendment No. 30 License No. DPR-36 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Maine Yankee Atomic Power Company (the licensee) dated March 3, 1977, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable mquirements have been satisfied.
4
-2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.B.(6)(b) of Facility Operating License No. DpR-36 is hereby amended to read as follows:
(b) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 3Q 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.
FOR THE NUCLEAR REGULATORY COMMISSION k
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Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 16,1977
ATTACHMENT TO LICENSE AMENDMENT N0. 30 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise the Appendix A-Technical Specifications as follows:
Remove Page Insert New Page 5.8-3 5.8-3 6
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a equipment do not exceed the pertiner.: values specified in Appendix B, Tabic 1 of 10 CFR Part 20.
7.
Protection fneters shall not be assigned in excess of those li st ed in T;.bi c 5. 8-1.
If, in the future,10 CFR 20, Section 103, shall assign protection 8.
factors fer resr:ratory and other protective equipe. cat, the provisions of paragranh 5.5. A shall be superseded by the provisions of 10 CFR 20, Section 103.
For radioactive micrials designated "Sub" in the "Isciope" column 8.
of Appendix 3. T: Ic I, Column 1 of IC CFR 70, tbc cencentrat.on value specified is based upon exposure to the materic! as an external rt.diation s% rec.
Individual c.xposures to these natcricls shall be of the linitation on individual Cose in (20.101.
accounted for as part These materials shall be subject to applicahic process ar.d other engineerin; Controls.
Paragraph 20.203 "Crution signs, label s, si gnal s, and control s".
In lieu B.
of the " control device" or "alarn signal" required by para, raph 20.203(c)(2),
q cach high radiction area in which the intensity of radiatien is 1000 nrc:/hr or less shall be barricaded and conspicuously post ed as a hirh rcdiation arca and entrance thereto shall be centrolled by requiring issucace of a P.adiation Any individual or group of individaals perd:ted to ent ei such h*ork Permit'.
areas shall be provided with one or.. ore of the following:
A radiat ion monitoring device thich continuously inJic.tes the radiation 1.
dose rate in the area.
A radiaticn r.cnitoring device which continuously in cgrates the radiation 2.
dose rate in the area and al.m as when a preset integrated dose is received.
Entry into such areas uith this r.onitoring, device nay be nade after the dose rat e Icvcis in the aren h:vc been established and personnel have been made knowledgcabic of them.
A health physics qualified individual (i.e. qualified in radiation protection 3.
procedures) uith a radiation dose rate tonitoring device who is responsibic for providinr. poritive control over the activities within the area and who the frcquency specified will perforn periodic radia:5cn surveillance at The surveillance frequency will be established by the Plant in the RWP.
llcal th Physi ci st.
The above procedure shall also apply to cach high radiation arca in which the In addition, locked doors intensity of radiation is greater than 1000 cre:n/hr.
shall be provided to prevent unauthcriced entry into such areas and the Leys shall be maintained under the administrative control of the shift sapervisor on duty and/or the Plant llealth Physicist.
from the RKP issuance requirement during f
- llealth Physics personnel shall he exempt the perfornance of their assir.ned radiation prot ect ion duties, providine they are
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into high radiation are,s.i radistionprotectionp[roceduresforentry foll owi n"o plant S
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