ML20149E632
| ML20149E632 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 12/31/1987 |
| From: | Zech G NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20149E635 | List: |
| References | |
| TAC-00077, TAC-00078, TAC-00079, TAC-77, TAC-78, TAC-79, NUDOCS 8801130418 | |
| Download: ML20149E632 (15) | |
Text
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NUCLEAR REGULATORY COMMISSION p
WASHINGTON, D. C. 20555
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TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-259
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PRCbHS FERRY NUCLEAR PLANT,IJNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendtrent No.139 License No OPR-33 1.
The Nuclear kegulatory Comission (the Comission) has found that:
A.
The application fer amendrent by Tennessee Valley Authority (the licensee) dated June 2, 1987, complies with the standards and requirerrents of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulatices 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 Cernrission; C.
There is reasonable assurance (i) that the activities authorized by tilis arrendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliar.ce 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 recuirements have been satisfied.
8801130418 871231 DR ADOCK O 29
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license arendment and paragraph 2.C.(2) of Facility Operating License No. PPR-33 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B as rcvised through Amendnent No.139, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specification.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuence.
FOR THE NUCLEAR REGULATORY CCt'. MISSION
&k Gary G. Zech Assistant Director for Projects TVA Projects Division Of fice of Special Projects
Attachment:
Changes to the Technical Specifications Date of issuance: December 31, 1987 4
ATTACHMENT TO LICENSE AMEKDMENT NO.139 FACILITY OPERATING LICENSE N0. DPR-52 0CCKET NO. 50-260 Revise the Appendix A Technical Scecifications by removino the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned ameridment number and contair. carginal lines indicating the area of change. Overleaf pages* are prnvided to maintain document ccmpleteness.
REF0VE THSERT 6.0-21 6.0-21 6.0-21 6.0-22*
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with the requirements of 10 CFR 20.
This radiation protection prograta shall b s organized to meet the requirements of 10 CFR 20 except in lieu of the "control device" or "alarm signal" required by paragraph 20.203 (c) of 10 CFR 20.
6.8.3.1 Each high radiation area in which the intensity of radiation is greater chan 100 meem/hr but less than or equal to 1000 arem/he shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiological. Work permit.* Any individual or group of individuals permitted to enter such aress shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area, b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeablo of them, c.
An individual qualified in radiation protection proceduras who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiological Work Permit.
6.8.3.2 Each nigh radiation area in which the intensity of radiation is greater than 1,000 mrem /he shall be subject to the provisions of (1) above; and, in addition, access to the source and/or area BFN Uni 1 6.0-21 Amendment !;0. 123, 139
8 shall be secured by lock (s).
The key (s) shall be under the administrative control of the shift engineer.
In the case of a high radiation area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be substituted for permanent access control.
- Health Physics personnel, or personnel escorted by Health Physics personnel, in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with appcovad.. radLation. protection.
procedures for entry it.to high radiation areas.
QUALITY ASSURANCE PROCEDURES - ETFLUENT AND 'dNVIh0NMENTAL MONITORING 6.8.4 Quality Assurance procedures shall be established, implemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1 June 1974 and Regulatory Guide 4.1, Rev. 1, April 1975 or Regulatory Guide 4.15, Dec. 1977.
6.0-22 Amendment No. 132, 138 BFN Unit 1
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 135 License No. DPR-52 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for avendment by Tennessee Valley Authority (the licensee) dated June E, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
l and the Comission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility vill operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission;
{
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and i
safety cf the public, and (ii) th6t 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 requirerents have been satisfied.
2.
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 Operatina License No. OPR-52 is hereby arended to read as follows:
(2) Technical Specification _s The Technical Specifications contained in Appendices A and B, as revised through Amendrent No.135. are hereby inccrporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall te implemented within 30 days from the date of issuance.
FOR THE hUCLEAR REGULATORY COMM!SSION Lu Gary 'G
- Zech, ssistant Director for Projects TVA Projects Division Office of Special Projects Attachtrent:
Charges to the Technical Specifications Date of Issuance: December 31, 1987 I
ATTACFPENT TO LICENSE AMENDPENT NO.135 FACIllTY OPERATING LICENSE N0. OPR-33 DOCKET !!O. 50-259 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided te raintain dccument completeness.
REMOVE INSERT 6.0-21 6,0-21 i
6.0-22 6.0-22*
l
with the requirements of 10 CFR 20.
This radiation protection program shall be organized to meet the requirements of 10 CFR 20 except in lieu of the "control device" or "alarm signal" required by paragraph 20.203 (c) of 10 CFR 20.
6.8.3.1 Each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than or equal to 1000 mrem /hr l
shall be barricaded and conspicueesly posted as a high radiation area and entrance thereto shall be controlled by requiring l
issuance of a Radiological Work Permit.* Any individual or j
group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
j a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
An individual qualified in radiation protection procedures c.
who is equipped with a radiation dose rate monitoring device.
This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiological Work Permit.
6.8.3.2 Each high radiation area in which the intensity of radiation is greater than 1,000 meem/hr shall be subject to the provisions of (1) above; and, in addition, access to the source and/or area BFN nit 2 6.0-21 Amendment No. 134, 135
shall be secured by lock (s).
The key (s) shall be under the j
administrative control of the shift engineer.
In the case of a high radiation area established for a period of 30 days or less, direct surveillance to present unauthorized entry may be j
substituted for permanent access c:^ trol.
- Health Physics personnel, or personnel escorted by Health Physics personnel, in accordance with approved emer5ency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection dultes. provided.they comply with approved radiation protection procedures for entry into high radiation areas.
QUALITY ASSURANCE PROCEDURES - EFFLUENT AND ENVIRONMENTAL MONITORING l
6.8.4 Quality Assurance procedures shall be establishuf, it,lemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Rev.1, June 1974 and Regulatory Guide 4.1, Rev. 1. April 1975 or Regulatory Guide 4.15, Dec. 1977.
l 6.0-22 Amendment No. 128, 134 BFN Unit 2
,P g* *E%go UNITED STATES
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I,j NUCLEAR REGULATORY COMMISS)ON y,, 7
{. A " ). E WAS4 tNG TO N, 0. C. 20555
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l TENNESSEE VALLEY AUTHORITY DCCKET NO. 50-296, BROWNS FERRY NUCLEAR PLANT,llNIT 3 AMENDMENT TO FACILITY OPERATING LICEhSE Amendment.'lo.110 License %. DPR-68 1.
The Nuclear Regulatory Comission (the Comission) has found tha..
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 2, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Cormiission'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, anc the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by j
this amendment can be conducted without endancering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; 0.
The issuance of this amendirent 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 requirements have been satisfied.
.-.,w
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y e
l 2-f 2.
Acccrdingly, the license is amended by changes to the Technical i
Specifications as irdicated in the attachment to this license anendment and paragraph 2.C.(r) of Facility Operating License No. NR-69 is hereby wended to read as follows:
(2) Technical Specificttions The Technical Specifications contained in Appendices A and B, es revised through An.endnent No.110 are hereby incorporated in the i
license. The licensee shall operate the facility in accordance with i
the Technical Specificationt,.
i l
3.
This license amendment is effective as of its cate of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION a
N L*
w
<~
Gary G.' ech, Assistaar. Director for Projects TVA Projects Division Office of Special Projects i
Attachment:
Changes to the Technical i
Specifications Date of Issuance: December 31, 1987 l
ATTACHMENT TO LICENSE APENDMENT NO.110 FACILITY OPERATING LICENSE NO. OPR-68 DOCKET NO.50-29C Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified 'y the captioned an<ndment number and contain marginal o
lir.es indicating the area of change. Overleaf pages* are provided to riaintain document completeness.
REMOVE INSERT 6.0-21 6.0-21 6.0-22 6.0-22*
- l
1 with the requirements of 10 CFR 20.
This radiation protection program shall be organized to meet the requirements of 10 CFR 20 except in lieu of the "control device" or "alarm signal" required by paragraph 20.203 (c) of 10 CFR 20.
6.8.3.1 Each high radiation area in which the intensity of radiation is 1
greater than 100 meem/hr but less than or equal to 1000 meem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiological Work Permit.* Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the ares.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This individual shall be responsible for providing j
positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiological Work Permit.
6.8.3.2 Each high radiation area in which the intensity of radiation is i
greater than 1,000 mrem /he shall be subject to the provisions of (1) above; and, in addition, access to the source and/or area BFN Unit 3 6.0-21 Amendment NO. 109, 110
1 shall be secured by lock (s).
The key (s) shall be under the administrative control of the shift engineer.
In the case of a high radiation area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be substituted for permanent access control.
- Health Physics per.'onnel, or personnel escorted by Health Physics personnel, in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
QUALITY ASSURANCE PROCEDURES - EFFLUENT AND ENVIRONMENTAL MONITORING 6.8.4 Quality Assurance procedures shall be established, implemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1. June 1974 and Regulatory Guide 4.1, Rev. 1, April 1975 or Regulatory Guide j
4.15, Dec. 1917.
l 6.o-22 Amendment tio. 203, 109 BFN Unit 3
,-4