ML20128B820
| ML20128B820 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/25/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128B826 | List: |
| References | |
| NUDOCS 8507030359 | |
| Download: ML20128B820 (14) | |
Text
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UNITED STATES y
g(g-9 g, NUCLEAR REGULATORY COMMISSION 5.,
j WASHINGTON, D. C. 20555
[,7 TENNESSEE VALLEY AUTHORITY DOCKET NO.-50-327 SE000YAH NUCLEAR PLANT, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Araendment No. 40 License No. DPR-77 1.
The Nuclear Regulatory Ccmmission (the Commission) has found that:
A.
The applications for amendment to the Sequoyah' Nuclear Plant, Unit I (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated August 19 and October 24, 1983, and February 22, 1984, ccmply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; C.
There is reasonable assurance (1) that the activities authorized by
(
this amendment can be conducted without endangering the health and I
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.
l 2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amend-l ment, and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby l
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as, revised through Amendment No. 40, are hereby incorporated into the license.
i g7030359850625 ADOCK 05000327 p
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h-The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1Ah M
Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Appendix A Technical Specification Changes Date of Issuance: June 25, 1985 e
e 4
ATTACHMENT TO LICENSE AMENDMENT N0.40 FACILITY OPERATING LICENSE N0. DpR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amended Page 3/4 3-55 B3/4 4-6 O
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INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
a.
With the number of OPERABLE accident monitoring instrumentation channels, except for the RCS subcooling margin monitor, less than l
the Required Number of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the number of OPERABLE accident monitoring instrumentation channels less than the MINIMUM CHANNELS OPERABLE requirements of Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
With the subcooling margin monitor inoperable for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the minimum shift crew (per Table 6.2-1) will be increased by one member who shall be dedicated to and capable of determining the sub-cooling margin during an accident using existing intrumentation.
SURVEILLANCE RE0VIREMENTS 4.3.3.7 Each accident monitoring instrumentation channel shall be demon-strated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
SEQUOYAH - UNIT 1 3/4 3-55 Amendment No. 40 v
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REACTOR COOLANT SYSTEM BASES 3/4.4.9 PRESSURE / TEMPERATURE LIMITS The temperature and pressure changes during heatup and cooldown are limited to be consistent with the requirements given in the ASME Boiler and Pressure Vessel Code,Section III, Appendix G.
1)
The reactor coolant temperature and pressure and system heatup and cooldown rates (with the exception of the pressurizer) shall be limited in accordance with Figures 3.4-2 and 3.4-3 for the first full power service period.
a)
Allowable cc.nbinations of pressure and temperature for specific temperature change rates are below and to the right of the limit lines.shown.
Limit lines for cooldown rates between those presented may be obtained by interpolation.
b)
Figures 3.4-2 and 3.4-3 define limits to assure prevention of non-ductile failure only.
For normal operation, other inherent plant characteristics, e.g., pump heat addition and pressurizer heater capacity, may limit the heatup and cooldown rates that can be achieved over certain pressure-temperature ranges.
2)
These limit lines shall be calculated periodically using methods provided below.
3)
The secondary side of the steam generator must not be pressurized above 200 psig if the temperature of the steam generator is below 70 F.
4)
The pressurizer heatup and cooldown rates shall not exceed 100 F/hr and 200 F/hr respectively.
The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 560 F.
l 5)
System preservice hydrotests and in-service leak and hydrotests shall be performed at pressures in accordance with the requirements of ASME Boiler and Pressure Vessel Code,Section XI.
The fracture toughness properties of the ferritic materials in the reactor vessel are determined in accordance with tne NRC Standard Review Plan, and ASTM E185-73, and in accordance 'with additional reactor vessel require-ments.
These properties are then evaluated in accordance with Appendix G of the 1976 Summer Addenda to Section III of the ASME Boiler and Pressure Vessel Code and the calculation methods described in WCAP-7924-A, " Basis for Heatup and Cooldown Limit Curves, April 1975."
SEQUOYAH - UNIT 1 B 3/4 4-6 Amendment No. 40
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fg UNITED STATES
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NUCLEAR REGULATORY COMMISSION 5,
- j WASHINGTON, D. C. 205S5 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE000YAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. DPR-79 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applications for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated August 19 and October 24, 1983, December 10, 1981, and February 22, 1984, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; C.
There is reasonable assurhnce (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 sa#ety 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.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 2.C.(2) of Facility Operating License No. OPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 32, are hereby incorporated into trie 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.
FOR THE NUCLEAR REGULATORY COMMISSION i
q
/M 11nor G. Adensam, Chief Licensing Branch No. 4 Division'of Licensing
Attachment:
Appendix A Technical Specification Changes Date of Issuance:
June 25, 1985 9
O we - - -..- -.- -
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ATTACHMENT TO LICENSE AMENDMENT NO. 32 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical-lines indicating the areas of change.
Amended Page 3/4 3-56 3/4 3-66 3/4 3-67 3/4 6-23 3/4 7-48 B3/4 4-6 4
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INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
a.
With the number of OPERABLE accident monitoring instrumentation channels, except for the RCS subcooling margin monitor, less than l
the Required Number of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the number of OPERABLE accident monitoring instrumentation channels less than the MINIMUM CHANNELS OPERABLE requirements of Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
With the subcooling margin monitor. inoperable for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the. minimum shift crew (per Table 6.2-1) will be increased by one member who shall be dedicated to and capable of determining the sub-cooling margin during an accident using existing intrumentation.
SURVEILLANCE REQUIREMENTS 4.3.3.7 Each accident monitoring instrumentation channel shall be demon-strated OPERABLE by performance of the CHANNEL CHECK ano CHANNEL CALIBRATION coerations at the frequencies shown in Table 4.3-7.
SEQUOYAH - UNIT 2 3/4 3-56 Amendment No. 32
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TABLE 3.3-11 (Continued) y FIRE DETECTION INSTRUMENTS 8
FIRE MINIMUM INSTRUMENTS OPERABLE e
ZONE INSTRUMENT LOCATION Ionization Photoelectric Thermal Infrared C*
241 480-V XFMR Rm. IA, E1. 749 3
242 480-V XFMR Rm. IA, El. 749 3
243 480-V XFMR Re. IB, El. 749 3
244 480-V XFMR Re. IB, E1. 749 3
245 480-V XFMR Rs. 2A, E1. 749 3
246 480-V XFMR Re. 2A, El. 749 3
247 480-V XFMR Rs. 2B, E1. 749 3
248 480-V XFMR Rm 28, El. 749 3
1 249 125-V Batt. Rm. I, E1. 749 1
250 125-V Batt. Rm. I, E1. 749 1
F51 125-V Batt. Rs. II, El. 749 1
w 252 125-V Batt. Rm. II, E1. 749 1
)
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253 125-V Batt. Rm. III, E1. 749 1
w 254 125-V Batt. Rs. III, El. 749 1
a 255 125-V Batt. Rs. IV, El. 749 1
256 125-V Batt. Rm. IV, El. 749 1
257 480-V Bd. Re. 18, E1, 749 4
258 480-V Bd. Rm. 18, E1. 749 4
259 480-V Bd. Rm. IA, El. 749 4
260 480-V Bd. Re. IA, El. 749 4
261 480-V Bd. Rm. 2A, E1. 749 4
262 480-V Bd. Rm. 2A, El. 749 4
263 480-V Bd. Re. 28, El. 749 4
264 480-V Bd. Rm. 28, El. 749 4
269 Computer Rm. El. 685 4
P.
270 Computer Rm. E1. 685 4
E 271 liux. Inst. Rm. El. 685 8
272
' Aux. In'st. Rm. El. 685 9
5 273 Computer Rm. Corridor, E1. 685 3
2 276 Intake Pump Sta. El. 690 & 670.5 15 277 ERCW Pump Sta. El. 704 21 w
427 125-V Batt. Rm. V El. 749 2
428 125-V Batt. Rm. V El. 749 2
T TABLE 3.3-11 (Continued)
E S
FIRE DETECTION INSTRUMENTS E
i FIRE MINIMUM INSTRUMENTS OPERABLE ZONE INSTRUMENT LOCATION Ionization Photoelectric lhermal Infrared N
296 Aux. CR Bds. L-48, 4D, & 11B El 732 6
297 Main CR Bds. El. 732 9
1 2%
Common MCR Bds. El 732 9
387 Turbine Cont. Bldg. Wall, El. 706 18 353 Lwr. Compt. Coolers, E1. 693 4
355-Upr. Compt. Coolers, E1. 778 4
374 Reactor Building Annulus 18 375 Reactor Building Annulus 18 362 RCP 1 El. 693 2*
363 RCP 1 El. 693 2
w1 358 RCP 2 E1. 693 2*
359 RCP 2 E1. 693 2
wa 366 RCP 3 E1. 693 2*
i 367 RCP 3 E1. 693 2
370 RCP 4 E1. 693 2*
371 RCP 4 El. 693 2
1 1
a i
e 2
j P
- This change is effective upon completion of the modification M
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TABLE 3.6-2 (Continued)
X; CONTAINMENT ISOLATION VALVES e
SE VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds)
E C.
PHASE "A" CONTAINMENT VENT ISOLATION (Cont.)
13.
FCV-30-50 Upper Compt Purge Air Exh 4*
-d 14.
FCV-30-51 Upper Compt Purge Air Exh 4*
15.
FCV-30-52 Upper Compt Purge Air Exh 4*
16.
FCV-30-53 Upper Compt Purge Air Exh 4*
17.
FCV-30-56 Lower Compt Purge Air Exh 4*
18.
FCV-30-57 Lower Compt Purge Air Exh 4*
19.
FCV-30-58 Inst Room Purge Air Exh 4*
20.
FCV-30-59 Inst Room Purge Air Exh 4*
21.
FCV-90-107 Cntet Bldg LWR Compt Air Mon 5*
22.
FCV-90-108 Cntat Bldg LWR Compt Air Mon 5*
23.
FCV-90-109 Cntet Bldg LWR Compt Air Hon 5*
24.
FCV-90-110 Cntet Bldg LWR Compt Air Mon 5*
25.
FCV-90-111 Cntet Bldg LWR Compt Air Hon 5*
u, 3:
26.
FCV-90-113 Cntmt Bldg LWR Compt Air Mon 5*
27.
FCV-90-114 Cntmt Bldg LWR Compt Air Mon 5*
y, R3 28.
FCV-90-115 Cntet Bldg LWR Compt Air Mon 5*
29.
FCV-90-116 Cntmt Bldg LWR Compt Air Mon 5*
30.
FCV-90-117 Cntat Bldg LWR Compt Air Mon 5*
i D.
OTHER 1.
FCV-30-46 Vacuum Relief Isolation Valve 25 2.
FCV-30-47 Vacuum Relief Isolation Valve 25 3.
FCV-30-48 Vacuum Relief Isolation Valve 25 I
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- Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with power removed and leakage limits of Surveillance Requirement 4.6.3.4 are satisfied.
r' E
- Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with 4
power removed and either FCV-62-73 or FCV-62-74 is maintained operable.
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PLANT 3YSTEMS FIRE HOSE STATIbMS LIMITING CONDITION FOR JPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-5 shall be OPERABLE.
APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to oe OPERABLE.
ACTION:
a.
With one or more of the fire hose stations shown in Table 3.7-5 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inoperable fire hose is the primary means of. fire suppression; other-wise, route the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Restore the fire hose station to OPERA 3LE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability, and plans and schedule for aestoring the station to OPERABLE status, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.11.4 Each of the fire hose stations shnwn in Table 3.7-5 shall be demonstrated OPERABLE:
a.
At least once per 31 days by a visual inspection of the fire hose stations accessible during plant operations to assure all required equipment is at the station.
b.
At least once per 18 months by:
1.
Visual inspection of all the stations not accessible during plant,
operations to assure all required equipment is at the station.
2.
Removing the hose for inspection and re racking, and 3.
Inspecting all gaskets and replacing any degraded gaskets in the couplings.
c.
At least unce per 3 years by:
1.
Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.
2.
Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.
SEQUOYAH.- UNIT 2 3/4 7-48 Amendment No. 32
REACTOR COOLANT SYSTEM BASES SPECIFIC ACTIVITY (Continued)
Reducing T,yg to less than 500 F prevents the release of activity should a steam generator tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves.
The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action.
Information obtained on iodine spiking will be used to assess the parameters associated with spiking phencmena.
A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.
3/4.4.9 PRESSURE / TEMPERATURE LIMITS
-The temperature and pressure changes during heatup and cooldown are limited to be consistent with the requirements given in the ASME Boiler and l
Pressure Vessel Code,Section III, Appendix G.
1)
The reactor coolant temperature and pressure and system heatup and cooldown rates (with the exception of the pressurizer) shall be limited in accordance with Figures 3.4-2 and 3.4-3 for the first full power service period.
e)
Allowable combinations of pressure and temperature for specific temperature change rates are below and to the right of the limit lines shown.
Limit lines for cooldown rates between those presented may be obtained by interpolation, b)
Figures 3.4-2 and 3.4-3 define limits to assure prevention of non-ductile failure only.
For normal operation, other inherent plant characteristics, e.g., pump heat addition and pressurizer heater capacity, may limit the heatup and cooldown rates that can be achieved over certain pressure-temperature ranges.
2)
These limit lines shall be calculated periodically using methods provided below.
3)
The secondary side of the steam generator must not be pressurized above 200 psig if the temperature of the steam generator is below 70 F.
4)
Thepressurizerheatupandcooldownratesshallnotexceed106F/hrand 200*/hr respectively.
The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 560 F.
l SEQUOYAH - UNIT 2 B 3/4 4-6 Amendment No. 32