ML20216J533
| ML20216J533 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (NPF-49-A-148) |
| Issue date: | 09/03/1997 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216J539 | List: |
| References | |
| NUDOCS 9709170354 | |
| Download: ML20216J533 (8) | |
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UNITED STATES a
P; NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3084H001
\\..... /j NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.148 License No. NPF-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated June 30, 1997, complies wita the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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.
9709170354 970903 PDR ADOCK 05000423 P
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l 2.
Accordingly, the license is amended by changes to d
- Technical Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(2)llows:of Facility Operating License No NPF-49 is hereby amended to read as fo
.(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
148. and the Environmental Protection Plan contained 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 NUCLEAR REGULATORY COMMISSION F /71 L 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 3,1997
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. ATTACHMENT TO LICENSE AMENDMENT NO.148 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 i
Replacethefollowingherevisedpagesareidentifiedbyamendmentnumbera the attached pages.
T contain vertical lines indicating the areas of change.
1 Remove Insert 3/4 7-9 3/4 7-9 B 3/4 7-5 B 3/4 7-5 B 3/4 7-6 B 3/4 7-6 l
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l PLANT SYSTEMS MAIM STIAN LIME ISOLATION VALVE 1 LINITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve (MSIV) shall be OPERABLE.
APPLICABILITY:
MODE 1 MODES 2, 3, and 4*,
except when a MSly is closed and l deactivated.
AWQti:
MODE It With one MSIV inoperable, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; otherwise be in MODE 2 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> MODES 2, 3, and 4:
With one or more MSIVs inoperable, subsequent operation in MODE 2, or 3 or 4 may proceed provided the inoperable isolation valve (s) are closed STANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowingl within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and verified closed once per 7 days. Otherwise, be in HOT 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Separate condition entry is allowed for each MSIV.
SURVE!LLANCE REQUIREMENTS 4.7.1.5.1 In MODES I and 2, each MSIV shall be demonstrated OPERABLE, pursuant to Specification 4.0.5, by verifying a partial stroke in MODES 1 or 2, or a full closure per Surveillance 4.7.1.5.2.
4.7.1.5.2 In MODE 3, each MSIV shall be demonstrated OPERABLE, pursuant to Specification 4.0.5, by verifying full closure within 10 seconds on an actual or simulated actuation signal when full stroke tested in MODES 3 or 4.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
4.7.1.5.3 In MODE 4 with the RCS temperature greater than or equal to 320 degrees Fahrenheit *, each MSly shall be demonstrated OPERABLE, pursuhnL to Specification 4.0.5, by verifying full closure within 120 seconds on an actual or simulated actuation signal when full stroke tested in MODE 4.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 4.
- In MODE 4, the MSIVs are required to be closed and deactivated with RCS temperature less than 320 degrees Fahrenheit.
NgLSTONE-UNIT 3 3/479 AmendmentNo.JJ,pp,JJJ. 177,148
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PLANT SYSTDtl 1
BASES 3/4.7.1.5 MAIN STEAN LINE ISOLATION VALVtt (continued)
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- This LC0 requires that four MSIVs in the steam lines be OPERA 8LE. The MSIVs are considered OPERABLE when the isolation times are within limits, and they close on an isolation actuation signal.
This LC0 provides assurance that the MSIVs will perfom their. design safety function to mitigate the consequences of accidents that could result in offsite exposures comparable to the 10CFR100 limits or the NRC Staff approved licensing
- basis, 4
APPLICABILITY j
- The MSIVs must be OPERABLE in MODE 1 and in MODES 2, 3, and 4 except when closed l and deactivated when there is significant mass and energy in the RCS and steam generators. When the MSIVs are closed, they are already performing the safety function.
The MSIVs must be OPERABLE in MODE 4 exce)t when closed and deactivated.
In MODE 4 with Reactor Coolant System tempera 4ure greater than or equal to 320'F, the MSIVs shall close within 120 seconds to ensure that the accident analysis assumptions are met.
A temperature greater than or ecual to 320'F has been specified because the steam energy is sufficient to prov'de the notive force to operate the MSIVs.
i In MODE 5.or 6, the steam generators do not contein much energy because their temperature is below the boiling point of water; therefore, the MSIVs are not 4
required for isolation of potential high energy secondary system pipe breaks in these MODES.
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With one MSIV inoperable in MODE 1, action must be taken to restore OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Some repairs to the MSIV can be made with the unit hot.
l The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is reasonable, considering the low probability of an accident-occurring during this time period that would require a closure of the 1
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is greater than that normally allowed for containment
. isolation valves-because-the MSIVs are valves that isolate a closed system penetrating containment. These valves differ from other containment isolation valves in that the closed system provides a passive barrier for containment isolation.
MILLSTONE - talli 3 8 3/4 7 5-Amendment No. J#, JM,148 em l
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PLANT SYSTEMS l
BASES 114.7.1.5 MAIN STEAN LINE ISOLATION VALVES fcontinued) j 4
If the MSIV cannot be restored to 0PERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the plant must be placed in a MODE in which the LC0 does not apply.
To achieve this status, the unit must be placed in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The Completion Times are reasonable, based on operating experience, to reach MODE 2 and to close the MSIVs in an orderly manner and without challenging plant systems.
i MODft 2. 3. and 4 f
Since the MSIVs are required to be OPERABLE in MODES 2, 3, and 4, the inoperable MSIVs may either be restored to 0PERABLE status or closed. When 4
closed, the MSIVs are already in the position required by the assumptions in the safety analysis.
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is consistent with that allowed in MODE 1.
for inoperable MSIVs that cannot be restored to OPERABLE status within the specified Completion Time, but are closed, the inoperable MSIVs must be 4
verified on a periodic basis to be closed.
This is necessary to ensure that the assumptions in the safety analysis remain valid. The 7 day vertftcation time is reasonable, based on engineering judgment, in view of MSIV status indications available in the control room, and other administrative controls, to ensure that these valves are in the closed position.
1f the MSIVs cannot be restored to OPERABLE status or are not closed within 4
the associated Completion Tiu.a. the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed at least in MODE 3 within 6 hourt, and in MODE 5 within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from MODE 2 conditions in an orderly manner and without challenging unit systems. 1he Action Statement is modified by a note indicating that separate condition entry is allowed for each MSIV.
SURVEILLANCE REQUIREMENTS i
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4.7.1.5.1 This surveillance performs a partial stroke test in MODES 1 or 2.
The partial stroke test shows that the MSIV's actuation solenoid valves operate in the proper amount of time.
In addition, the part stroke test shows that the main valve is free to move. This provides reasonable assurance that the MSIV will operate as assumed in the accident analysis. This surveillance is normally erformed during full power operation with the plant at suitable i
(appropriate conditions (e.g., pressure and temperature).
In addition, if the closure ime of the MSIV is less than 10 seconds when verified in accordance with Specification 4.7.1.5.2, the OPERABILITY demonstration of the MSIV in MODES 1 or 2 is not required per Specification 4.7.1.5.1.
1 MI,L,LSTONE - UNIT 3 B3/47-6 Amendment No. J#, JM,148 4
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BASES i
SURVflLLANCE Rf0VIRIMENTS feontinued) 4.7.1.5.2 This surveillance demonstrates that MS!V closure time-is less than 10 seconds on an actual or simulated actuation signal in MODE 3, when tested 1
pursuant to specification 4.0.5.
A simulated signal is defined as any of the following engineering safety features actuation system instrumentation i
functional units per Technical Specifications Table 4.3 2: 4.a.1) manual initiation, individual, 4.a.2 manual initiation system, 4.c. containment pressure high 2, 4.d. steam l)ne pressure low, qr-4.e. steam line pressure -
i negative rate high. The MS!V closure time is assumed in the accident analyses.
This surveillance is normally performed upon returning the plant to operation following a refueling outage.
The test is normally conducted in HDDES3or4with".heplantatsuitable[ appropriate) conditions (e.g.,
pressure and temperature) delay of testing untti the pro
>er operatingThis survelliance requirement is modified by exception which allows a
_ conditions are met, or until it is desired to operate tie valves.
This exception to Specification 4.0.4 would also allow the MS!Vs to be cycled to i
demonstrate post repair OPERABILITY.
In addition, if the closure time of the MSIV is less than lo seconds when verified in accordance with Specification i
4.7.1.5.2, the OPERABILITY demonstration of the MS!V in MODES 1 or 2 is not required per Specification 4.7.1.5.1.
4.7.1.5.3 This surveillance verifies that MSIV closure time is less than 120 seconds on an actual or simulated actuation signal in MODE 4, with the RCS temperature greater than or equal to 320 degrees Fahrenheit, when tested pursuant to specification 4.0.5.
The MSIVs are required to be closed and deactivated with the RCS less than 320 degrees Fahrenheit in MODE 4.
A simulated signal is definkd as any of the following engineering safety features actuation system instrumentation functional units per Technical specifications Table 3.4-2: 4.a.1 manual initiation, individual, 4.a.2 initiation,systam4.c. con)tainment pressure low, or 4.e. steam line pressure pressure high 2 manuti i
negative rate high.
The MSIV closure time is assumed in the accident analyses.
This surveillance only applies in MODE 4, at an RCS temperature greater than or equal to 320 degrees fahrenheit, because the MSIVs are steam operated and a minimum steam pressure is required to operate the valve.
The test is normally conductedinMODE4withtheplantatsuitable(appropriate)beopenedor 1
conditions (e.g.,pressureandtemperature).
If the valves are not to energized in MODE 4, the surveillance is not performed. -This surveillance requirement is modified by an exception which allows a delay of testing until the pro valves.per operating conditions are met, or until it is desired to operate the This exception to Specification 4.0.4 would also allow the MSIVs to be cycled-to demonstrate post repair OPERABILITY.
In addition, if the closure time of the MSIV is less than lo seconds when verified in accordance with Specification 4.7.1.5.3.-the OPERABILITY demonstration of the MSly in MODES 1, 2, or 3 is not required per Specification 4.7.1.5.1 and 4.7.1.5.2.-
gLSTONE-UNIT 3 B3/47-6a
_ Amendment No. J M, 148
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PLANT SY$TEMS 4
BA$ts 3/4.7.2 STEAM CENERATOR 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 RTuo, of 60'F and are sufficient to prevent brittle fracture.
3/4.7.3 REACTOR PLANT COMPONENT COOLING WATER SYSTEM The OPERABILITY of the Reactor Plant 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 related equip-ment 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.
gl5 TONE.-UNIT 3 83/47-7 AmendmentNo.7#,148 J