ML19324B382
| ML19324B382 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 10/24/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19324B381 | List: |
| References | |
| NUDOCS 8911060181 | |
| Download: ML19324B382 (17) | |
Text
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NUCLE AR REGULATORY COMMISSION
..r W A&HINGT ON, D. C. 20666
%,.....,e CONNECTICUT YAAKEE ATOMIC POWER COMPANY L
DOCKET NO. 50 213 HADDAv. NECK PLANT l
AMENDMENT TO FAtlLITY OPERATING LICENSE Amendment No. 124 l
License No. DPR 61 1.
The Nuclear Regulatory Comission (the Comission) has found that:
f A.
The application for amendment by Connecticut Yankee Atomic Power (the licensee), dated April 25, 1989 as supplemented June 26, 1989, complies with the standards and requirements of the Atomic Energy l
Act of 1954, as aewnded (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will 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 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 j
E.
The issuance of this amendment is in accordance with 10 CFR Part El j
of the Comission's regulations and all applicable requirements have been satisfied.
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2 2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the atta,che.ent to this license asiendment, and paragraph 2.C.(2) of Facility Operating License No. DPR 61 is hereby j
anended to read as fo110ms-(2) Technical Srecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 24 The licensee shall op{erate the facility in accordance with the, are hereby inc; Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULA ORY COMMISSION
/
Jo njh Stolz, Director Projkct Directorate I.4 Division of Reactor Projects. 1/II I
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
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Specifications Date of Issuance: October 24, 1989 i
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ATTACHMENT TO LICENSE AMENDMENT NO.124 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendrent number and contain vertical lines indicating the areas of change.
Ryemove Insert i
6-20 6-20 6-20a l
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I ADMINISTRATIVE CONTROLS j
t 5.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR part 20 and shall be approved, maintained and t.
adhered to for all operations involving personnel radiation exposure.
6.12 SUPERSEDED BY 10 CFR 20.103(c) and (f) ON DECEMBER 28, 1977 6.13 HIGH RADIATION AREA 6.13.1 Pursuant to paragraph 20.203 c (5) of 10 CFR Part 20, in lieu of the
" control device" or " alarm signal" re(qu) ired by paragraph 20.203(c), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the'
+
radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.
Any i
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 area; or b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integratad dose is received.
Entry 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 ir.ade knowledgeable of them; or c.
An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health Physics Supervisor in the RWP.
6.13.2 In addition to the requirements of Specification 6.13.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall De maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision.
Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area; and the maximum allowable stay time for individuals in that area.
In lieu of the stay time specification of the RWP, direct or remote (such as 6-20 Amendment Nos. 25,79, 124
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a closed circuit TV cameras continuous surveillance may be made by personnel qualified in radiation pr)otection procedures to provide positive exposure control over the activities being performed within the area.
For individual high radiation areas accessible to personne1' with radiation levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no' enclosure can be reasonably constructed around the ir.dividual area, that individual area shall be barricaded, censpicuously posted, and a flashing light shall be activated as a warning device, j
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i 6 20a Amendment No. 124
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NUCLEAR REGULATORY COMMISSION v.
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NORTHEAST NUCLEAR ENERGY COMPANY J
DOCKET NO. 50-245 s
MILLSTONE NUCLEAR POWER STATION, UNIT NO. I j
AMENDMERT TO FACILITY OPERATING LICENSE Amendment No. 35 4
L License No. DPR-21 i
l 1.
The Nuclear Regulatory Commission (the Commission) has'found that:
A.
The application for amendment by Connecticut Yankee Atomic Power (the licensee), dated April 25, 1989, as supplemented June 26, 1989, complies with the standards and requirements of the Atomic Energy l
Act of 1954, as amended (the Act), and the Commission's rules and l
regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the c
. provisions of the Act, and the rules and regulations of the L
Conmission; t
l C.
There is ressonable assurance (i) that the activities authorized by this amendnent 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 comr.on l
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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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-21 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Arendment No. 35, 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 issuance, to be impleinented within 30 days of issuance.
F THE NUCLEAR REGU ORY COMMISSION Stolz, Directo i
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et Directorate I*f/
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sion of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 24, 1989 L
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t ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO. DPR-21
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DOCKET NO. 50-245 i
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
i Remove Insert iii 111 6-21 6-21 6-22
.6-22 7
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1 Surveillance Paae No.
1 3.11 REACTOR FUEL ASSEMBLY 4.11 3/4 11-1 A. Average Planar Linear Heat Generation Rate (APLHGR)................... A.....
3/4 11-1 B. Linear Heat Generation Rate (LHGR)...........
B.....
3/4 11-2 C. Minimum Critical Power Ratio (MCPR).......... C.....
3/4 11-3 i
3.12 FIRE PROTECTION SYSTEMS 3/4 12 1 r
A. Fire Suppression Water System............... A.....
3/4 12-1 B. Spray and/or Sprinkler Systems.............. B.....
3/4 12-5 C. Carbon Dioxide and Halon 1301 Systems....... C..... 3/4 12-7 D. Fire Hose Stations.......................... D.....
3/4 12-9 E. Fire Protection Instrumentation............. E...... 3/4 12-13 F. Penetration Fire Barriers................... F...... 3/4 12-17 3.13 INSERVICE INSPECTION 4.13 3/4 13-1 3.14 PLANT SYSTEMS 4.14 3/4 14-1
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5.0 DESIGN FEATURES 5-1 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 Responsibility................................. 6-1 6.2 Organization (Offsite and Onsite)...............
6-l' 6.3 Unit Staff Qualifications......................
6-4 6.4 Training.......................................
6-6 6.5 Review and Audit............................... 6-6 6.6 Reportabl e Event Action........................
6-15 6.7 Safety Limit Violation.........................
6-15 6.8 Procedures.....................................
6-16 i
6.9 Reporting Requirements.........................
6 17 6.10 Record Retention...............................
6-19a 6.11 Radiation Protection Program................... 6-20 6.12 High Radiation Area............................
6-21 6.13 Systems Integrity.............................
6-21a 6.14 lodine Monitoring..............................
6-21a 6.15 Radiological Effluent Monitoring and Offsite Dose Calculation Manual...........
6-21a 6.16 Radioactive Waste Treatment....................
6-22 l
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I iii Amendment Nos. 1,29,35 1
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l ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1 Pursuant to paragraph 20,203(c)(5} of 10 CFR Part 20, in lieu of the
" control device" or " alarm signal required by paragraph 20,203(c),
each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as i
a high radiation area and entrance thereto shall be controlled by
. requiring issuance of a Radiation Work Permit (RWP).
Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted.by such individuals may be exempt from the RWP issuance requirement during the perfor-mance of their assigned duties in high radiation areas with exposure l
rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such i
high radiation areas. 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 area; or i
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 a
monitoring device may be made after the dose rate levels in the L
I area have been established and personnel have been made knowl-l edgeable of them; or
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c.
An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health Physics Supervisor in the RWP.
6.12.2 In additio'n to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or Health Physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area.
In lieu of the stay time specification of the RWP, direct or remote (such as closed-circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being per-formed within the area.
Millstone Unit 1 6-21 Amendment Nos. f, 35
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ADMINISTRATIVE CONTROLS For individual high radiation areas accessible to personnel with radiation levels greater than 1000 mR/h that are located within large areas where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.
6.13 SYSTEMS INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would, or could, contain highly radioactive fluids during a serious transient, or accident, to as low as practical levels. This program shall include the following:
1.
Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at a frecuency not to exceed refueling cycle intervals.
6.14 IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:
1.
Training of personnel.
2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment, l
6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)
Section I, Radiological Effluent Monitoring Manual, shall outline the sampling and analysis programs to determine the concentration of radioactive materials i
released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of station operation. It shall also specify operating guidelines for radioactive waste i
treatment systems and report content.
1 Changes in Section I shall be submitted to the Commission for approval prior to implementation.
1 Section II, the Offsite Dose Calculation Manual (ODCM), shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these technical specifications.
I Changes to Section 11 need not be submitted to the Commission for approval prior to implementation, but shall be included in the next Semi-Annual Radio-active Effluent Release Report.
. Millstone Unit 1 6-21a
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l Ea 6.16 RADIDACTIVE WASTE TREATMENT I
Procedures for liquid and gaseous radioactive effluent discharges from
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the Unit shall be prepared, approved, maintained, and adhered to for all 5
operations involving offslte releases of radioactive effluents. These L
procedures shall specify the use of approprate* waste treatment utilizing n
the guidance provided in the REM 00CM
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- The solid radioactive waste treatment system shall be operated in accordance i
with the Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements.
L Millstone Unit 1 6-22 Amendment Nos. 1,35
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o UNITED STATES
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NUCLEAR REGULATORY COMMISSION
.I 3 s W ASHING TON, D. C. 20555
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NORTHEAST NUCLEAR ENERGY COMPANY e
THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILL STONE NUCLE AR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICCNSE l
Amendu.ent No. 144 License No. DPR-65 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Connecticut Yankee Atomic Power (the licensee), dated April 25, 1989, as supplemented June 26, 1989, 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 oper6te 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 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 requirements have been satisfied.
I' L
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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.C.(2) of Facility Operating License No. DPR-65 is hereby i
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.144, 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 issuance, to be implemented within 30 days of issuance.
THE NUCL GUL TORY COMMISSION oh h Sto z, Director
, r ject Directorate I-i Y1 vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Late of Issuance:0ctober 24,1989
e ATTACHMENT TO LICENSE AMENDMENT NO.144 FACILITY 0PERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 6-21 6-21 i
6-22 6-22 l
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ADMINISTRATIVE CONTROLS g.
Records of training and qualification for current members of the plant
- staff, t
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Records of inservice -inspections performed pursuant to these Technical Specifications, i.
Records 'of quality assurance activities required by the QA Manual.
J.
Records of reviews performed for ' changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR Part 50.59.
k.
Records of meetings of the PORC, the NRC, the SORC and the SNRB.
1.
Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with -
the requirements of 10 CFR - Part 20 and shall be approved,. maintained and adhered to for all operations involving personnel rediation exposure.
6.12 HIGH RADIATION AREA 6.12.1 Pursuant to paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the
" control device" or " alarm signal" required by paragraph 20.203(c), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance
- thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise follewing plant radiation protection procedures for entry into such high radiation-areas.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
l-a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area; or 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 levels in the area have been established and personnel have been made knowledgeable of them; or L
HILLSTONE - UNIT 2 6-21 Amendment Nos. 103, 104, 111, 144 order 10/24/80
o ADMINISTRATIVE CONTROLS c.
An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health Physics Supervisor in the RWP.
i i
6.12.2 In addition to the requirements of Specification 6.12.1, areas i
accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface whien the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or Health Physics supervision.
Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the tamediate work areas and the maximum allowable stay time for individuals in that area.
In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in I
radiation protection procedures to provide positive exposure control over the activities being performed within the area.
For individual high radiation areas accessible to personnel with radiation levels greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no. enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a l
flashing light shall be activated as a warning device.
6,13 SYSTEMS INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:
1.
Provisions establishing preventive maintenance and periodic visual inspection requirements, and I
2.
Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
6.14 IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the fc11owing:
1.
Training of personnel, 2.
Procedures for monitoring, and i
3.
Provisions for maintenance of sampling and analysis equipment.
Ogr gfg,144 MILLSTONE - UNIT 2 6-22 j
3