ML20148D900
| ML20148D900 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/29/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20148D908 | List: |
| References | |
| NUDOCS 9706020190 | |
| Download: ML20148D900 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20555 4001
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NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 i
MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 139 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated March 31, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as 4
amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, the i
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 i
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 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.
9706020190 970529 PDR ADOCK 05000423 P
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- ' 2.
Accordingly, the licerse 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. NPF-49 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 139, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto '.re hereby incorporated in the license.
The licensee shall cperate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
'3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION PhillipF.y McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 29, 1997
1 ATTACHMENT TO LICENSE AMENDMENT NO.139 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 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.
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Remove Insert 3/4 7-5 3/4 7-5 4
B 3/4 7-2 8 3/4 7-2 B 3/4 7-2a B 3/4 7-2a
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PLANT. SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 92 days on a STAGGERED TEST BASIS, tested pursuant to Specification 4.0.5, by:
1)
Verifying that on recirculation flow each motor-driven pump develops a total head of greater than or equal to 3385 feet; l l
2)
Verifying that on recirculation flow the steam turbine-driven pump develops a total head of greater than or equal to 3780 feet when the secondary steam supply pressure is greater than 800 psig. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
c.
At least once each REFUELING INTERVAL by verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of an Auxiliary Feedwater Actuation test signal.
For the steam turbine-driven auxiliary feedwater pump, the provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
4.7.1.2.2 An auxiliary feedwater flow path to each steam generator shall be demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days prior to entering MODE 2 by verifying flow to each steam generator.
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I NILLSTONE - UNIT 3 3/4 7-5 Amendment No. 77. 177 177, 139 0475
l PLANT SYSTEMS BASES l
SAFETY VALVES (Continued) i Minimum total steam flow rate capability of the operable MSSVs i
w, =.
i on any one steam generator at the highest MSSV opening pressure i
including tolerance and accumulation, as appropriate, in 1b/sec.
For example, if the maximum number of inoperable MSSVs on any l
one steam generator is one, then w, should be a summation of the i
capacity of the operable MSSVs at the highest operable MSSV operating pressure, excluding the highest capacity MSSV.
If the i
maximum number of inoperable MSSVs per steam generator is three, j
then w, should be a summation of the capacity of the operable i
MSSVs at the highest operable MSSV operating pressure, excluding the three highest capacity MSSVs. The following plant specific safety valve flow rates were used:
5 SG Safety Main Steam System Valve Number (Bank No.)
Set Pressure (psia)
Flow (1bm/hr per loop) 1 1200 893,160 2
1210 900,607 l
3 1220 908,055 4
1230 915,502 l
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1240 922,950 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 350*F from normal operating or accident conditions coincident with a total loss-of-offsite power.
The auxiliary feedwater system is capable of delivering a total feedwater flow of 480 gpm at a pressure of 1236 psia to the entrance of at least three steam generators while allowing for (1) any spillage through the design worst-case break of the Normal feedwater line, (2) the design worst-case single fail-ure; and (3) recirculation flow. This capacity is sufficient to ensure that i
adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350*F at which point the Residual Heat Removal System may be placed into operation.
Surveillance Requirement 4.7.1.2.1 verifies that each AFW pump's total head at a recirculation flow test point is greater than or equal to the required total head. This surveillance ensures that the AFW pump performance has not degraded during the operating cycle. Because it is undesirable to introduce cold AFW into MILLST0ME - UNIT 3 8 3/4 7-2 Amendment No. 197 139 un
l' PLANT SYSTEMS BASES 1
AUXILIARY FEEDWATER SYSTEM (Continued) i the steam generators while they are operating, this testing is performed with recirculation flow. This test confims one point on the pump curve and is indicative of overall performance. This test confirms component OPERABILITY is i
used to trend performance and to detect incipient failures by indicating abnormal perfonsance. The total head specified in Surveillance Requirement 4.7.1.2.1 does not include a margin for test measurement uncertainty. This consideration shall l
be addressed at the implementing procedure level.
l 3/4.7.1.3 DEMINERALIZED WATER STORAGE TANK l
The OPERABILITY of the domineralized water storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with steam discharge to the atmosphere l
concurrent with total loss-of-offsite power, and with an additional 6-hour cooldown period to reduce reactor coolant temperature to 350*F. The contained water volume limit includes an allowance for water not usable because of tank j
discharge line location or other physical characteristics.
3/4.7.1.4 SPECIFIC ACTIVITY The limitations on Secondary Coolant System specific activity ensure that the 4
resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a steam line rupture.
This dose i
also includes the effects of a coincident I gpm primary-to-secondary tube leak in the steam ger.arator of the affected steam line. These values are consistent with the assumptions used in the safety analyses.
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MILL 5T0NE - LMIT 3 5 3/4 7-2a Amendment No. 197.139 0476
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