ML20196B017
| ML20196B017 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/19/1998 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20196B021 | List: |
| References | |
| NUDOCS 9811300223 | |
| Download: ML20196B017 (11) | |
Text
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'4 UNITED STATES l
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NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 200 5 0001
<n TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 234 License No. DPR-77 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 30,1998, complies with the standards and requirements of the Atomic Energy l
Act of 1954, as amended (the Act), and the Commission's rules and regulations set l
iorth in 10 CFR Chapter I; B.
The facility will operate in confcnnity with the application, the provisions of the Act, and the rules and regulations of the Commission; 1
l C.
There is reasonable assurance (i) that the activities authorized by this amendment l
can be mnducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's l
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.
9811300223 981119 PDR ADOCK 05000327 P
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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. DPR-77 is hereby amended to read as follows:
(2) Technical Soecifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 239 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days after issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION I
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Frederick J. Hebdon, Director Project Directorate ll-3 Division of Reactor Projects -l/ll l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 19,1998 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 239 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by the captioned amendment number and contains a marginalline indicating the area of change.
REMOVE INSERT 3/4 4-4a 3/4 4-4a B 3/4 4-2a B 3/4 4-2a i..'
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RELIEF VALVES - OPERATING LIMITING CONDITION FOR OPERATION 3.4.3.2 Two power relief valves (PORVd) and their associated block valves l
shall be OPERABLE.
R16 APPLICABILITY: MODES 1, 2, and 3.
l ACTION:
1 a.
With one or more PORV(s) inoperable, but capable of RCS pressure R115 control, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve (s);- otherwise, be in at j
least HOT STANDBY 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 SHUTDOWF lR161 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
1 b.
With one PORV inoperable and incapable of RCS pressure control, l
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close R115 the associated block valve and remove power from the block valves restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY 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 R161 l
within the following G hours.
l c.
With both PORVs inoperable and incapable of RCS pressure control,
)
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore each of the PORVs to OPERABLE status R115 or close their associated block valves and remove power from the block valves and be in HOT STANDBY within the next 6. hours and NOT R161 SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d.
With one or more block valve (s) inoperable, within 1 hour:
(1) restore the block valve (s) to OPERABLE staltur, or close the block R115 valve (s). and remove power freut the block valve (s), or close the PORV(s) and remove power from its associated solenoid valve (s); and (2) apply the ACTION b. or c. above, as appropriate, for the isolkted PORV(s).
e.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.4.3.2.1 In addition to the requirements of Spucification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by a.
Performance of a CHANNEL CALIBRATION, and b.
Operating the valve through one complete cycle of full travel lR161 l-
.during Modes 3, 4,
or 5 with a steam bubble in the pressurizer.
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4.4.3.2.2 Each block valve shall be demonstrated OPERABLE at least once per 92 l
days by operating the valve through one complete cycle of full travel, i
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SEQUOYAH - UNIT 1 3/4 4-4a Amendment Nos. 12, 146, 111, t,
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REACTOR COOLANT SYSTEM BASES to cycle the valves when they have been closed to comply with the ACTION requirements. This precludes the need to cycle the valves with full system R161 differential pressure or when maintenance is being performed to restore an inoperable PORV to operable status.
Testing of PORVs with a steam bubble in the pressurizer is considered to be a representive tect for assessing PORV performance under normal operating conditions.
3/4.4.4 PRESSURIZER The limit on the maximum water volume in the pressurizer assures that the parameter is maintained within the normal steady state envelope of operation assumed in the SAR.
The limit is consistent with the initial SAR assumptions.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation. The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system. The requirement that 150 kw of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that the plant will R16 be able to control reactor coolant pressure and establish natural circulation conditions.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained.
The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
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l SEQUOYAH - UNIT 1 B 3/4 4-2a Amendment No, t2, 159, 230
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i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2006H001 o%[4*****,5 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. PM License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 30,1998, 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 (i) that the activities authorized by this amenciment 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 Commission's regulations and all applicable requirements have been satisfied.
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. DPR-79 is hereby amended to read as follows:
4 (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 229 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days after istuance.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdon irector Project Directorate ll-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changer to the Technical Specifications Date of issuance: fbwrtxr 19, 1998
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l' ATTACHMENT TO LICENSE AMENDMENT NO. 229 FACILITY OPERATING LICENSE NO. DPR-79 l
l DOCKET NO. 50-328 l !
k Revise the Appendix A Technical Specifications by removing the page identified below and L
inserting the anciosed page. The revised page is identified by the captioned amendment number and contains a marginal line indicating the area of change.
REMOVE INSERT 3/4 4-0 3/4 4-8 B 3/4 4-2a B 3/4 4-2a l
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REACTOR COOLANT SYSTEM EELIEF VALVES - OPERATING l
l LIMITING CONDITION FOR OPERATION 3.4.3.2 All power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
a.
With one or more PORV(s) inoperable, but capable of RCS pressure control, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status R101 or close the associated block valve (s); otherwise, be in at least NOT STANDBY 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 R147 l
following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one PORV inoperable and incapable of RCS pressure control, R101 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close the l
associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY 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 R147 following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With both PORVs inoperable and incapable of RCS pressure control, R101 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore each of the PORVs to OPERABLE status or close their associated block valves and remove power from the block valves and be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN R147 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d.
With one or more block valve (s) inoperable, within 1 hour:
(1) restore the block valve (s) to OPERABLE status, or close the block valve (s) and recove power from the block valve (s), or close the R101 PORV(s) and remove power from its associated solenoid valve (s); and (2) apply the ACTION b. or c. above, as appropriate, for the isolated PORV(s).
e.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.4.3.2.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by a.
Performance of a CHANNEL CALIBRATION, and b.
Operating the valve through one complete cycle'of full travel during l
Modes 3, 4,
or 5 with a steam bubble in.the pressurizer.
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l 4.4.3.2.2 Each block valve shall be demonstrated OPERABLE at least once per j
92 days by operating the valve through one complete cycle of full travel.
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l SEQUOYAH - UNIT 2 3/4 4-8 Amendment Nos. 94, MF1, 4+} 229 i-k t
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4 REACTOR COOL 7dI E.12.IEM l
BASES l
3/4.4s 2 and 3/4.4.3 SAFETY AND RELIEF VALVES (Continued) d.
Automatic control of PORVs,to control reactor coolant system pressure..This is a function that reduces challenges to the code safety valves for overpressure events, e.
Manual control of a block valve to isolate a stuck-open PORV.
R147 surveillance requirements (SR) provide assurance that the PORVs and block valves can perform their functions. The block valves are exempt from the SR to L
cycle the valves when they have been closed to comply with the ACTION l
requirements. This precludes the need to cycle the valves with full system j.
differential pressure or when maintenance is being performed to restore an inoperable PORV to operable status.
- Testing of.PORVs with a steam bubble in the pressurizer is considered to j
be a representive test for assessing PORV performance under normal operating conditions.
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3/4.4.4 PRESSURIZER The limit on the maximum water volume in the pressurizer assures that the parameter is maintained within the normal steady state envelope of operation assumed in the SAR.
The limit is consistent with the initial SAR assumptions.
~
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation.
The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system.
The requirement that 150 kw of pressu rizer heaters and their associated controls be capable.of being supplied electr ical power from an emergency bus provides assurance that the plant will be able to control reactor coolant pressure and establish natural circulation j
conditions.
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SEQUOYAH'- UNIT 2 B 3/4 4-2a Amendment No. WP, M 4
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