ML20096G219
| ML20096G219 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/18/1996 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20096G223 | List: |
| References | |
| NUDOCS 9601250049 | |
| Download: ML20096G219 (6) | |
Text
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UNITED STATES g:
j NUCLEAR REGULATORY COMMISSION 2
WAaHINGTON, D.C. 30005 4 001 4,.....
NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWEli COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR P0tfER STATION. UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.195 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated September 29, 1995, as e
supplemented November 9, 1995, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations 'of the Commission; 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 Comeission'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.
9601250049 960118 PDR ADOCK 05000336 P
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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, i
and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby j
amended to read as follows:
(2)
Technical Specifications The Technical Specifi afions contained in Appendix A, as. revised through Amendment No. W, are hereby incorporated in the i
license. The licensee shall operate the facility in accordance with the Technical Specifications.
i 3.
This license amendment is effective as of the date of issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMISSION Phillip McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 18, 1996
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ATTACHMENT TO LICENSE AMENDMENT NO.195 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Insert Remove 3/4 4-2 3/4 4-2 3/4 7-1 3/4 7 3/4 7-3 3/4 7-3
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REACTOR COOLANT SYSTEN i
j SAFETYVALVES LIMITIMB COMITION FOR OPERATION i
3.4.2.1 A minimum of one pressurizer code safety valve shall be OPERABLE with j
a lift setting
- of 2500 PSIA
- 35.**
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APPLLcARfLITY: MODE 4 when the temperature of any RCS cold leg is greater than i
275'P.
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AGIl(E:
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With no pressurizer code safety valve OPERABLE, immediately suspend all enrations involving positive reactivity changes and place an OPERABLE stutdown cooling loop into operation.
i 3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift setting
- of 2500 PSIA t 35.**
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APPLICABILITY: N0 DES 1, 2 and 3.
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AGIIM:
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With one pressurizer code safety valve inoperable, either restore the inoperable i
valve to OPERABLE status within 15 minutes or be in H0T SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIRENENTS 1
l 4.4.2 Each pressurizer code safety valve shall be demonstrated OPERABLE with a lift
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setting of 2500 PSIA i 15, in accordance with Specification 4.0.5.
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- The lift setting pressure shall correspond to ambient conditions of the valve (s) at nominal operating temperature and pressure.
- The lift setting shall be within i 15 following pressurizer code safety valve testing.
NILLSTONE - IBl!T 1 3/44-2 Amendment No. pp. JJ7. JP).195 0217 j
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3/4.7 PLAlff SYSTElis 2.4.7.1 TLpAI K CVt1E SAF M VALVES LIMITIIIB COMITIO11 FM OPERATIO11 3.7.1.1 All main steam line code. safety valves shall.'be OPERA 8LE.
APPLICARILITY MODES 1, l', and 3.
ET188 With both reactor coolant loops and associated steam generators in a.
operation and with one or more main steam line code safety valves inoperable, owration in M00ES 1 I, and 3 proceed provided, that within 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, either the inoperable va ve is restored to j
OPERABLE status or the Power Level-Nigh trip setpoint is reduced per Table 3.7 1 otherwise, be in at least NOT STAWSY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HDT SWTDOW within the following it hours.
I suRVEILLAlICE REQUIRMENS Each main steam line code safety valve shall be demonstrated 4.7.1.1 OPERABLE, with lift settings as shown in Table 4.7-1, in accordance
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with Specification 4.0.5.
3/471 Amendment No. 5. # 7. # 1, 195 nt.u. sr0nt - WIT a
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TABLE 4.7-1 STEAN LIIE SAFETY VALVES VALVE IRBRERS LIFT RETTINC* ft Mi**
a.
2-MS-246 & 2-MS-247 1000 psia b.
2-MS-242 & 2-MS-254 1005 psia c.
2-MS-245 & 2-MS-249 1015 psia d.
2-MS-241 & 2-MS-252 1025 psia e.
2-MS-244 & 2-MS-251 1035 psia i
f.
2-MS-240 & 2-MS-250 1045 psia g.
2-MS-239, 2-MS-243, 1050 psia 2-MS-248 & 2-MS-253
- The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
The lift setting shall be within t 15 following main steam line code safety valve testing.
MILL 5 TOME - IslIT t 3/47-3 Amendment No.195
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