ML20117K475
| ML20117K475 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/04/1996 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20117K477 | List: |
| References | |
| NUDOCS 9609110323 | |
| Download: ML20117K475 (5) | |
Text
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t UNITED STATES i
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E NUCLEAR REGULATORY COMMISSION i
WASHINGTON. D.C. 20666 4001 s,...../
NORTHEAST NUCLEAR ENERGY COMPANY 1
l THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY i
DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 202 i
License No. DPR-65 1
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy 1
Company, et al. (the licensee) dated March 28, 1996, complies j
with the standards and requirements of the Atomic Energy Act of i
1954, as amended (the Act), and the Comission's rules and I
regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the j
provisions of the Act, and the rules and regulations of the 1
Comission; l
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 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 Comission's regulations and all applicable requirements have been satisfied.
9609110323 960904 PDR ADOCK 05000336 P
. 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 "a
OPR-65 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 202, 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 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f F #/ L Phillipy.McKee, Director Northeast Utilities Project Directorate Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 4, 1996
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ATTACHMENT TO LICENSE AMENDMENT N0. 202 FACILITY OPERATING LICENSE NO. DPR-65 l
DOCKET NO. 50-336 Replace the following pages of the Appendix A, Technical Specifications, with j
the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
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Remove Insert I
3/4 7-19 3/4 7-19 83/4 7-5 B3/4 7-5 i
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PLANT SYSTEMS 3/4.7.7 SEALED SOURCE CONTAMINATION LIMITING ColelTION FOR OPERATION i
3.7.7.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gama emitting material or 5 microcuries of alpha emitting material shall be free of 2 0.005 microcuries of removable contamination.
APPLICABILITY: AT ALL TIMES.
ACTION:
a.
Each sealed source with removable contamination in excess of the above limit shall be imediately withdrawn from use and:
1.
Either decontaminated and repaired, or 2.
Disposed of in accordance with Comission Regulations.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.7.1.1 Test Reauirements - Each sealed source shall be tested for leakage and/or contamination by:
{
a.
The licensee, or b.
Other persons specifically authorized by the Comission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
4.7.7.1.2 Test Frecuencies - Each category of sealed sources shall be tested at the frequencies described below.
a.
Sources in use (excludino startuo sources oreviousiv sub.iected to core flux) - At least once per six months for all sealed sources containing radioactive material:
MILLSTONE - UNIT 2 3/4 7-19 Amendment No. JM, 202 0206
PLANT SYSTEMS BASES 3/4.7.7 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the source material.
The limitations on removable contamination for sources requiring leak testing, including alpha emitters,-is based on 10 CFR 70.39(a)(3) limits for plutonium.
Leakageofsourcesl excluded from the requirements of this specification represent less than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.
3/4.7.8 SNUBBERS I
All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall be determined and approved by the Plant Operations Review Comittee.
The determination shall be based upon the existing radiation levels and the expected time to perform
- a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recomendations of Regulatory Guide 8.8 and 8.10.
The addition or deletion of any hydraulic or mechanic snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may_ be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
MILLSTONE - UNIT 2 B 3/4 7-5 Amendment Nos. JJ, M, M. JJ7,202 0266
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