ML20217C116
| ML20217C116 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/11/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217C120 | List: |
| References | |
| NUDOCS 9710010200 | |
| Download: ML20217C116 (7) | |
Text
- _ _ _ _ _ - _ _ _ _ _ - - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _
gp carg p
t UNITED STATES s
]
NUCLEAR REGULATORY COMMISSION l
2 W ASHINGToN, D.C. 3086Hm01 NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 150 License No. NPF-49 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 June 19, 1997, 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 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 Ccmmission's regulations and all applicable requirements have been satisfied.
I fok iS$$ No
$3 P
A.
'- 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. NPF-49 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 150, and the Environmental Protection Plan conttined in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate 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 LEAR REGULATORY COMMISSION
/
Phillip F. McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 11, 1997
p.
ATTACHMENT TO LICENSE AMENDMENT NO.
150 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO.-50-423 Replace the followin the attached pages. g anges of the Appendix A, Technical Specifications, with 11e revised pages are identified b contain vertical lines indicating the areas of change. y amendment number and Remove hti 3/4 7-6 3/4 7-6 B 3/4 7-2 B 3/4 7-2 8 3/4 7-2a B 3/4 7-2a B 3/4 7-2b*
- Over flow page - no change
, PLANT SYSTEMS DEMINERALIZED WATER STORAGE TANK LIMITING ColeITION FOR OPERATION 3.7.1.3 : The domineralized water storage tank (DWST) shall be OPERABLE with a water volume of at least 334,000 gallons.
l APPLICABILITY: NODES 1, 2, and 3.
EllDH:
With the DWST inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:.
Restore the DWST to OPERABLE status or be in at least HOT STANDBY a.
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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or b.
Demonstrate the OPERABILITY of the condensate storage tank (CST) as a backup supply to the auxiliary feedwater pumps and restore the DWST to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s-and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIRENENTS 4.7.1.3.1 The DWST 'shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the water volume is within its limits when the tank is the supply l
source for.the auxiliary feedwater pumps.
4.7.1.3.2 The' CST shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the combined volume of both the DWST and CST is at least 384,000 gallons of water whenever the CST and DWST are the supply source for the auxiliary feedwater pumps.
NILLSTONE - UNIT 3 3/4 7-6 Amendment No.150 0634
PLANT SYSTEMS BASES SAFETY VALVES (Continued)
Minimum total steam flow rate capability of the operable MSSVs w,
on any one steam generator at the highest MSSV opening pressure including tolerance and accumulation, as appropriate, in 1b/sec.
For example, if the maximum number of inoperable MSSVs on any one steam generator is one, then w, should be a sumation of the capacity of the operable MSSVs at the highest operable MSSV operating pressure, excluding the highest capacity MSSV.
If the maximum number of inoperable MSSVs per steam generator is three, then w, should be a summation of the capacity of the operable HSSVs at the highest operable MSSV operating pressure, excluding the three highest capacity MSSVs.
The following plant specific safety valve flow rates were used:
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 3
1220 908,055 4
1230 915,502 5
1240 922,950 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater (AFW) System ensures a makeup water supply to the steam generators (SGs) to support decay heat removal from the Reactor Coolant System (RCS) upon the loss of normal feedwater supply, assuming the worst case single failure. The AFW System consists of two motor driven AFW pumps and one steam turbine driven AFW pump.
Each motor driven AFW pump provides at least 50% of the AFW flow capacity assumed in the accident analysis. After reactor shutdown, decay heat eventually decreases so that one motor driven AFW pump can provide sufficient SG makeup flow. The steam driven AFW pump has a rated capacity approximately double that of a motor driven AFW pump and is thus dufined as a 100% capacity pump.
Given the worst case single failure, the AFW System is designed to mitigate the consequences of numerous design basis accidents, including Feedwater Line Break, Loss of Normal Feedwater, Steam Generator Tube Rupture Main Steam Line Break, and Small Break Loss of Coolant Accident.
MILLSTONE - UNIT 3 B 3/4 7-2 Amendment No. Jpg, J77, 150 j
ons
- o.,
PLANT.5YSTLAS BASES-AUXILIARY FEEDWATER SYSTEM (Continued)
In addition, given the worst case failure, the AFW is designed to supply sufficient makeup water to replace SG inventory loss as the RCS is cooled 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 the steam generators while they are operating, this testing is performed with recirculation flow.
This test confirms one point on the pump curve and is indicative of overall performance. This test confirms component OPERABILITY is used to trend performance and to detect incipient failures by indicating abnormal performance. The total head specified in Surveillance Requirement 4.7.1.2.1 does not include a margin for test measurement uncertainty.
This consideration shall be addressed at the implementing procedure level.
3/4.7.1.3 DEMINERALIZED WATER STORAGE TANK The OPERABILITY of the domineralized water storage tank (DWST) with a 334,000 gallon minimum measured water volume ensures that sufficient water is available to maintain the reactor coolant system 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, concurrent with a total loss-of-offsite power, and with an additional 6-hour cooldown period to reduce reactor coolant temperature to 350*F. The 334,000 gallon required water volume contains an allowance for tank inventory not usable because of tank discharge line-location, other tank physical characteristics, and surveillance measurement uncertainty considerations. The inventory requirement is conservatively based on 120*F water temperature which maximizes inventory required-to remove RCS decay heat.
In-the event of a feedline break,-this inventory requirement includes an allowance for 30 minutes of spillage before operator action is credited to isolate flow to the line break.
If the combined condensate storage tank (CST) and DWST inventory is being credited, there are 50,000 gallons of unusable CST inventory due to tank discharge line location, other physical characteristics, level measurement uncertainty and potential measurement bias error due to the CST nitrogen blanket. To obtain the Surveillance Requirement 4.7.1.3.2's DWST and CST combined volume, this 50,000 gallons of unusable CST inventory has been added to the 334,000 gallon DWST water volume specified in LCO 3.7.1.3 resulting in a 384,000 gallons requirement (334,000 + 50,000 = 384,000 gallons).
MIgLSTONE-UNIT 3 8 3/4 7-2a Amendment No. JpJ. J M, 150
PLANT SYSTEMS BASES AUXILIARY FEEDWATER SYSTEM (Continued) 3/4.7.1.4 SPECIFIC ACTIVITY The limitations on Secondary Coolant System specific activity ensure that the 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 also includes the effects of a coincident I gpm primary-to-secondary tube leak in the steam generator of the affected steam line. These values are consistent with the assumptions used in the safety analyses.
MILLSTONE - UNIT 3 B 3/4 7-2b Amendrant No. 777 J77,1 W l 0635
_