ML20210N788
| ML20210N788 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/03/1987 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Connecticut Light & Power Co, Northeast Nuclear Energy Co (NNECO), Western Massachusetts Electric Co |
| Shared Package | |
| ML20210N794 | List: |
| References | |
| DPR-65-A-115, GL-85-019, TAC 63349 NUDOCS 8702130217 | |
| Download: ML20210N788 (11) | |
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UNITED STATES 8
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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.115 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated October 29, 1986 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; 8.
The facility will operate in coriformity 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 i
this amendment can be conducted without endangering the health and safety ci 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 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.
8702130217 E70203 PDR ADOCK 05000 6
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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 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.115, 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.
FOR THE UCLEAR REGULATORY COMMISSION 9L/M' Ashok. Thadani, Dir h PWR P oject Directorate #8 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: February 3, 1987 i
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ATTACHMENT TO LICENSE AMENDMENT NO.115 FACILITY OPERATING 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 is identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are provided to maintain document completeness.
Remove Page Insert Page 3/4 4-13 3/4 4-13 3/4 4-14 3/4 4-14 g
8 3/4 4-4 B 3/4 4-4 6-18 6-18 6-19 6-19
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REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant sha be limited to:
a.
1 1.0 pCi/ gram DOSE EQUIVALENT I-131, and b.
5 100/E pCi/ gram.
APPLICABILITY: MODES 1, 2, 3, 4 and 5.
ACTION:
MODES 1, 2 and 3*:
a.
With the specific activity of the primary coolant > 1.0 pCi/ gram k
DOSE EQUIVALENT I-131 but within the allowable limit (below and to the left of the line) shown on Figure 3.4-1, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The provisions of Specification 3.0.4 are not applicable, j
b.
With the specific activity of the primary coolant > 1.0 pC1/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with Tavg < 515 F within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
c.
With the specific activity of the primary coolant > 100/E pCi/ gram, be in HOT STANDBY with T,yg < 515*F within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
MODES 1, 2, 3, 4 and 5:
d.
With the specific activity of the primary coolant > 1.0 pCi/ gram DOSE EQUIVALENT I-131 or > 100/E pCi/ gram, perform the sampling and analysis requirements of item 4 a) of Table 4.4-2 until the specific activity of the primary coolant is restored to within its limits.
- With Tavg 515*F.
MILLSTONE - UNIT 2 3/4 4-13 Amendment No. 9,JJJ,115
REACTOR COOL. ANT SYSTEM SURVEILLANCE-REQUIREMENTS a
l 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sainpling and analysis program of Table 4.4-2.
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1 MILLSTONE - UNIT 2 3/4 4-14 Amendment No.115
BASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE i
j 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant j
Pressure Boundary. These detection systems are consistent with the recomendations of Regulatory Guide 1.45, " Reactor Coolant Pressure i
Boundary Leakage Detection Systems."
l 3/4.4.6.2 REACTOR COOLANT SYSTEM LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this i
leakage can be reduced to a threshold value of less than 1 GPM. This i
threshold value is sufficiently low to ensure early detection of l~i additional leakage.
The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a i
limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage l
detection systems.
The total steam generator tube leakage limit of 1 GPM for all steam '
generators ensures that the dosage contribution from the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The 1 GPM l
limit is consistent with the assumptions used in the analysis of these j
accidents.
~ PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it i
j nay be indicative of an impending gross failure of the pressure boundary.
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l'herefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the l
l unit to be promptly placed in COLD SHUTDOWN.
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MILLSTONE - UNIT 2 B 3/4 4-3 i,
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REACTOR' COOLANT SYSTEM BASES 3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System contaminants ensure that corrosion of the Reactor Coolant System is minimized and reduce the poten-tial for Reactor Coolant System leakage or failure due to stress corrosion.
Maintaining the concentrations of the contaminants within the Steady State Limits shown on Table 3.4-1 provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient.
Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.
k The surveillance requirements provide adequate assuranco that concentra-tions in excess of the limits will be detected in sufficient time to take corrective action.
3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam genarator leakage rate of 1.0 GPM and a concurrent loss of offsite electrical power.
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity > 1.0 uCi/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, acconinodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.
MILLSTONE - UNIT 2 B 3/4 4-4 Amendment No.115
ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the PORC/SORC, as applicable, and approved by the Unit Superintendent / Station Superintendent within 14 days of implementation.
6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REM 0DCM.
6.8.5 All procedures and procedure changes required for the Radiological Environmental Monitoring Program of 6.8.4 above shall be reviewed by an.
individual (other than the author) from the Radiological Assessment Branch or the Production Operation Services Laboratory (POSL) and approved by g
appropriate supervision.
Temporary changes may be made provided the intent of the original proce-dure is not altered and the change is documented and reviewed by an individual (other than the author) from the Radiological Assessment Branch or the POSL, within 14 days of implementation.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10. Code of Federal Regulations, the following reports shall be submitted to Regional Administrator, Region I, U.S. Nuclear Regulatory Commission, unless otherwise noted.
STARTbP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a compari-sdn of these values with design predictions and specifications. Any addi-tional specific details required in license conditions based on other commit-ments shall be included in this report.
MILLSTONC - UNIT 2 6-17 Amendment No. J9,28,36,H,93, M Ill,
ADMINISTRATIVE CONTROLS 6.9.1.3 Startup reports shall be submitted within (1) 90 days following comple-tion of the startup test program, (2) 90 days following resumption or commence-ment of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL REPORTSE 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and thejr associated man-rem exposure according to work and job functions,9 e.g., reactor operations and surveillance, l
inservice inspection, routine maintenance, special maintenance (describe
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maintenance), waste processing and refueling. The dose assignment to i
l various duty functions may be estimates based on pocket dosimeter, TLD or film badge measurements. Small exposures totalling less than 20% of i
the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
b.
The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.5.b).
c.
The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine perfonned prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than the limit.
Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
y A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
2/ This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
MILLSTONE - UNIT 2 6-18 Amendment No. #,JJJ,115,
ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Management, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, with a copy to the Regional Administrator, Region I, U. S. Nuclear Regulatory Commission, no later than the 15th of each month following the calendar month covered by the report.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region I, U. S. Nuclear Regulatory Commission, within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
a.
Inoperable Seismic Monitoring Instrumentation, Specification
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3.3.3.3.
b.
Inoperable Meteorological Monitoring Instrumentation, Specification-3.3.3.4.
c.
Safety Class 1 Inservice Inspection Program Review, Specification 4.4.10.1.
d.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
e.
Fire Detection Instrumentation, Specification 3.3.3.7.
f.
Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.
g.
RCS Overpressure Mitigation, Specification 3.4.9.3.
h.
Radiological Effluent Reports required by Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3, and 3.11.4.
I 1.
Degradation of containment structure, Specification 4.6.1.6.4.
l j.
Steam Generator Tube Inspection, Specification 4.4.5.1.5.
g MILLSTONE - UNIT 2 6-19 Amendment No. JS,7J JSA.JJJ,115,
ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level, b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTABLE EVENTS.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of reactor tests and experiments.
f.
Records of changes made to operating procedures, g
g.
Records of radioactive shipments.
h.
Records of sealed source leak tests and results.
1.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the facility operating license:
a.
Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of facility radiation and contamination surveys, d.
Records of radiation exposure for all individuals entering radiation control areas, e.
Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
MILLSTONE - UNIT 2 6-20 Amendment No. 9,36,7Gh8,111,