ML20235K401
| ML20235K401 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/25/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20235K404 | List: |
| References | |
| DPR-65-A-119 NUDOCS 8710050076 | |
| Download: ML20235K401 (9) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION l
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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.119 License No. DPR-65 1.
The Nuclear Regulatory Comission (the Comission) has found that:
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The applications for amendment by Northeast Nuclear Energy Capany,'
et,al. (the licensee), dated July 14,1987(supplementedbyletter dated July 31,1987) and August 3,1987, comply 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 conformity 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
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this amendment can be conducted without endangering the health and safety of the public, and (11) 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
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The issuance of this amendment is in accordance with 10 CFR Part 51 l
of the Comission's regulations and all applicable requirements have been satisfied.
8710050076 870925 PDR ADOCK 05000336 P
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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 7acility 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. :119, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective following initial entry into MODE 4 I
prior to operating in Cycle 9.
i FOR THE NUCLEAR RE ULAT'RY COMMISSION
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Jo n F. Stolz, Direct r P ject Directorate I-4 fvision of Reactor Pro;fects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 25, 1987
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4 ATTACHMENT TO LICENSE AMENDMENT NO.119 -
FACILITY OPE, RATING LICENSE N0; DPR-65
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,f(CKETNO.50-336 1,,
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. Replace the'followin the er, closed pages. g pages of.ithe Appendix A Technical Specifications with The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Remove Insert i
- 3/4 7-17 3/4 7-17 6/19 6/19
.6/23 6/23 6/24
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HANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.
Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2500 cfm 110 %
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2.
Verifying within 31 days af ter removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978. The carbon sample shall have a removal efficiency of 295 percent.
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3.
Verifying a system flow rate of 2500 cfm110% during system operation when tested in accordance with ANSI N510-1975.
d.
Af ter every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days af ter removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory i
Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978,
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meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
e.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA I
filters and charcoal adsorber banks is less than 6 inches Water l
Gauge while operating the system at a flow rate of 2500 efn 110 %
4 2.
Verifying that on a recirculation signal, the system I
automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.
3.
Verifying that control room air in-leakage is less than 100 scfm at a AP of 1/16" of Water Gauge.
f.
Af ter each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2500 cfm 110 %
MILLSTONE - UNIT 2 3/4 7-17 Amendment Nos. 25,72,100,119 i
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 9 After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2500 cfm + 10%.
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MILLSTONE - UNIT 2 3/4 7-18 Amendment No. 71,100 h
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ADMINISTigr; /E CONTROLS Documentation of all f ailures (inability to lift or reclose within the d.
tolerances allowed by the design basis) and challenges to the pressurher PORVs or safety valves.
MONTHLY OPER ATING 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. 20553, with a copy to the Regional Administrator, Region 1, U.S. Nuclear Regulatory Commission, no later than the ISth of each month following the calendar month covered by the report.
SPECIAL REPORTS Special reports shall be submitted to the Regional Administrator, 6.9.2 Region 1, U. S. Nuclear Regulatory Commission, within the time period specified These reports shall be submitted covering the activities for each report.
identified below pursuant to the requirements of the applicable reference specification:
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
a.
b.
Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
c.
Safety Class 1
inservice Inspection Frogram
- Review, Specification 4.4.10.1.
d.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
Fire Detection Instrumentation, Specifications 3.3.3.7.
e.
Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.
f.
i RCS Overpressure Mitigation, Specification 3.4.9.3 g.
h.
Radiological Ef fluent Reports required by Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3 and 3.11.4.
Degradation of containment structure, Specification 4.6.1.6.4.
i.
f Steam Generation Tube Inspection, Specification 4.4.5.1.5.
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MILLSTONE - UNIT 2 6-19 Amendment Nos. 36,93,194,111,115, 119
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ADMINISTRATIVE CONTROLS l
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 rep 0RTABLE 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.
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 r.ew 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.
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e.
Records of gaseous and liquid radioactive material released to the environs.
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Records of transient or operational cycles for those facility l
components designed for a limited number of transients or cycles.
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s MILLSTONE - UNIT 2 6-20 Amendment No. 7,M, M 111
l ADMINISTRATIVE CONTROLS 6.15 RADIOLOGICAL EFFLUEB 1 MONITORING AND OFFSITE DOSE
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CALCULATION MANUAL (REMODCM) i'Section I, Radiological Effluer.ts Monitoring Manual, shall outline the sampling and analysis programs to determine the concentration of radioactive materials j
- 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 treatment systems l
and report content.
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I Changes to Section I shall be submitted to the Commission for approval prior to f
implementation.
Section 11, 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 calculations of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCOs contained in these technical specifications. Changes to Section 11 need not be submitted to the Commission for approval prior to implementation, but she!! be included in the next Semi-Annual Radioactive Effluent Release Report.
6.16 RADIOACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the unit shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents, These procedures shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REMODCM.
The Solid Radioactive Waste Treatment system shall be operated in accordance with the Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements.
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6.17 SECONDARY WATER CHEMISTRY A program shall be maintained for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shallinclude:
1.
Identification of a sampling schedule for the critical variables and control points for these variables, 2.
Identification of the procedures used to measure the values of the critical variables, 3.
Identification of process sampling points, which shallinclude monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, 4.
Procedures for the recording and management of data, MILLSTONE - UNIT 2 6-23 Amendment Nos. 104,171,119
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ADMINISTR/.TIVE CONTROLS Procedures defining corrective actions for all off-control point 5
chemistry conditions, and 4
A procedure identifying: (a) the authority responsible for the 6.
interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
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MILLSTONE - UNIT 2 6-24 Amendment No. 119
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