ML20217G736
| ML20217G736 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/02/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217G739 | List: |
| References | |
| NUDOCS 9710140179 | |
| Download: ML20217G736 (6) | |
Text
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pu rvy A'*,
y UNITED STATES s
j NUCLEAR REGULATORY COMMIS$10N e'
WAaHINGTON, D.C. 3066H001 f
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NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 E STONE NUCLEAR POWER STATION. UNIT NO. 3
/4ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 151 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 July 18, 1997, complies with tne standards and requirements of the Atomic Energy Act er 1954, e.s amended (the Act), and the Commission's rules and replations 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 Conmissica; C.
There is reasonable assurance (i) that the activities authc.-ized by this amendrent 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 regulaticas; D.
The issuance of this amendmer.t 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 i. in accordance with 10 CFR Part 51 of the Conession's regulations and all applicable requirements have been satisfied.
9710140*79 971002 PDR A!..'CK 05000423 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, 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.151, and the Environmental Protection Plan contained in Appendix B, both of which are atta:hed 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 NUCLEAR REGULATORY COMMISSION styFR7L Phillip F. McKee Deputy Director fo: Licensing Special Projects Office
~
Office of Nuclear Reactor Regulation
Attachment:
Changes to the-Technical Specifications Date of Issuance: October 2, 1997
ATTACHMENT TO LICENSE AMENDMENT NO. 151 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following anges of the Appendix A, Technical Specifications, with the attached nages. T.1e revised pages are identified by amendment number and contain vertical lines indicating the areas of change, Remove Insert 3/4 7-9a B 3/4 7-7 B 3/4 7-7 B 3/4 7-7a*
- overflow page - no change
q-PLANT SYSTEMS STEAM GENERATOR ATMOSPHERIC RELIEF BYPASS LINES LIMITING CONDITION FOR OPERATION 3.7.1.6 Each steam generator atmospheric relief bypast. valve shall be OPERABLE, with the associate / main steam atwospheric re(SGARBV) line lief isolation
-(block) valve in the open position, i
APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS a.
With one required SGARBV line ino)erable, restore required SGARBV line to OPERABLE status within 7 days or ae in at least MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in MODE 4 without reliance upon steam generator for heat removal within the next 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
1.00 3.0.4 is not applicable, b.
With two or more required SGARBV lines inoperable, restore all but one required SGARBV line to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and be in MODE 4 without reliance upon steam generator for heat removal within the next 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.6.1 Verify one complete cycle of each SGARBV every 18 months, 3
4.7.1.6.2 Verify one comolete cycle of each main steam atmospheric relief isolation (block) valve every 18 months.
MILLSTONE - UNIT 3 3/47-9a Amendment No.151 l
osa
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j PLANT SYSTEMS
. BASES i
l 3/4.7.1.6 STEAM GENERATOR ATMOSPHERIC RELIEF BYPASS LINES l
The OPERABILITY of the steam go.nerator atmospheric relief bypass valve (SGARR) lines rupture (SGTR) provides a method to recover from a steam generator tube j
event during which the operator is required to perform a l
limited cooldown to establish adequate subcooling as a necessary step to limit i
the primary to secondary break flow into the ruptured steam generator. The time required to limit the primary to secondary break flow for an SGTR event i
is more critical than the time required to cooldown to RHR entry conditions.
Because of these time constraints, these valves and associated flow paths must i
be OPERABLE from the control room. The number of SGARBVs required to be i.
OPERABLE from the control room to satisfy the SGTR accident analysis requires i
consideration of single failure criteria. Four SGARBV are required to be OPERABLE to ensure the credited steam release pathways available to conduct a j
unit cooldown following a SGTR.
i For other design events, the SGARBVs provide a safety grade method for cooling the unit to residual heat removal (RHR) entry conditions should the i
preferred heat sink via the steam bypass system or the steam generator j
atmospheric relief valves be unavailable.
Prior to operator action to cooldown, the main steam safety valves (MSSVs) are assumed to operate i
automatically to relieve steam and maintain the steam generator pressure below design limits.
I Each SGARBV line consists of one SGARBV and an associated block valve (main steam atmupheric relief isolation valve, 3 MSS *MOV18A/B/C/0). These block valves are used in the event a steam generator atmospheric relief valve j
(SGARV) or SGARBV fails to close. Becau e of the electrical power relationship between the SGARBV and the block valves, if a block valve is L
maintained closed, the SGARBV flow path is inoperable because of single failure consideration.
The bases for the required actions can be found in NUREG 1431, Rev. 1.
The LCO APPLICABILITY and ACTION str.tements uses the terms " MODE 4 when steam generator is relied upon for heat removal" and "in MODE 4 without reliance upon steam generator for heat removal." This means that those steam generators which are credited for decay heat removal to comply with LCO 3.4.1.3-(Reactor Coolant System. Hot Shutdown) shall have an OPERABLE SGARBV line. See Bases Section 3/4.4.1 for more detail.
'3/4.7.2 -STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 70'F and 200 psig are based on a steam generator RTuor of 60'F and are sufficient to prevent-brittle fract m.
MILLSTONE - UNIT 3 8 3/4 7-7 Amendment No. JM. 177,351 0649
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PJ ANT SYSTEMS BASES 3/4.7.3 REACTOR PL ANT COMPONENT C00LINC-WATER SYSTEM l
The OPERABILITY of the Reactor Piant Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
3/4.7.4 SERVICE WATER SYSTEM The OPERABILITY of the Service Water System ensures that sufficient cooling capacity is available for continued operation of safety-reinted equip-ment during normal and accident cor.ditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
l MILLSTONE - UNIT 3 8 3/4 7-7a Amendment No. 151 l
0549
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