ML20236D140
| ML20236D140 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-79-A-095, DPR-79-A-95) |
| Issue date: | 03/10/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236D141 | List: |
| References | |
| NUDOCS 8903220481 | |
| Download: ML20236D140 (8) | |
Text
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- g ustoqk, UNITED STATES
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,g NUCLEAR REGULATORY COMMISSION I
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j WASHINGTON, D. C. 20655 k*****
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO' FACILITY OPERATING LICENSE l
bPR-79 n
o i
i 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the i
licensee) dated December 2, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
J 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 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 1
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.
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8903220481 890310 DR ADOCK 05000320 p
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2.
Accordingly.thelicenseisamendedbychangestotheTechnical 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, 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.
FOR THE NUCLEAR REGULATORY COMMISSION I
l i
l Emt an e lack, Assistant Director f.
or Projects A
TVA Projects Division Office of Nuclear. Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT NO. 95 l
FACILITY OPERATING LICENSE NO. DPR-79' l
DOCKET NO. 50-328 i
Revise'the Appendix A Technical Specifications by removing the pages identified below and inserting the enciesed pages..The revised pages are identified by the captioned amendment number and contain marginal
- lines-indicating the area of change.
REMOVE INSERT 3/4 2-4 3/4 2-4 3/4 2-5 3/4 2-5 3/4 2-6 3/4 2 3/4 2-6a 3/4 2-6a j
3/4 5-4 3/4 5-4 4
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POWER'0 DISTRIBUTION LIMlTS I
3/4.2.2 HEATFLUXHOTCHANNELFACTOR-FfZj i
LIMITING CONDITION FOR OPERATION i
3.2.2 F (Z) shall be limited by the following relationships:
9 F (Z) < [2.237 ] [K(Z)] for P > 0.5 9.
p i
F (Z) < [1.52.237 ] [K(Z)] for P < 0.5 Q
I THERMAL POWER where P = RATED THERMAL POWER and K(Z) is the function obtained from Figure 3.2-2 for a given core height location.
J APPLICABILITY:
MODE 1 ACTION:
i With F (Z) exceeding its limit:
9 Reduce THERMAL POWER at least 1% for each 1% F (Z) exceeds the limit a.
q within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the' next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION I
may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower Delta T Trip Setpoints (value of K ) have been reduced at least 1% (in AT span)'for each 1% F (Z) 1 4
q exceeds the limit.
b.
Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; THERMAL POWER may then be increased provided F (Z) is demonstrated'through incore mapping-to be within q
its limit.
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SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not' applicable.
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- See Page 3/4 2-6a i
SEQUOYAH - UNIT 2 3/4 2-4 Amendment No. 2195 -
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. POWER DISTRIBUTION LIMITS
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SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.2 F (z)'shall be evaluated to determine if F (Z) is within its limit i
q q
by:
a.
Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.
j b.
' Increasing the measured F (z) component of;the power distribution q
map by 3 percent to; account for manufacturing tolerances and further increasing the value by 5% to account.for measurement uncertainties.
i c.
Satisfying the following relationship:
N F (z) < 2.237 x K(z) for P > 0.5 4
F x W(z)
F (z) $,W(z) x 0.5 2.237 x K(z) for P > 0.5 where F (z) is measured F (z) increased by the allowances for q
manufacturing tolerances and measurement uncertainty, F limit is q
the F limit,.K(z) is given in Figure 3.2-2, P is the relative q
THERMAL POWER, and W(z) is the cycle dependent function.that 9
accounts for power distribution transients encountered during normal operation.
This function is given in the Peaking Factor Limit Report as per Specification 6.9.1.14.
4 d.
Measuring F (z) according to the following schedule:
1.
Upon achieving equilibrium conditions after exceeding by-10 percent or more of RATED THERMAL POWER, the THERMAL POWER 1
at which F (z)"was last determined,* or q
2.
At least once per 31 effective full power days, whichever-occurs first.
- During power escalation at the beginning of each cycle, power level may be increased until a power level for extended operation has been achieved and a power distribution map obtained.
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- See Page 3/4 2-6a SEQUOYAH.- UNIT 2 3/4 2-5 Amendment No. 21, 95
P0k'ER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) e.
With measurements indicating M
~
maximum F (z) q j
over z K(z) has increased since the previous determination of F (z) either of the following actions shall be taken-1.
F (z) shall be increased by 2 percent over that specified in 4.2.2.2.c, or 2.
F (z) shall be measured at least once per ' effective full power days until 2 successive maps indicata that maximum F (z) is not increasing.
over z K(z)
(b f.
With the relationships specified in 4.2.2.2.c above not being satisfied:
1.
Calculate the present F (z) exceeds its limit by the following expression:
q "M
F (z) x W(z) maximum g
-1 x 100 for P > 0.5 1
A y
~
over z 2.237 x K(z)
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y F (z) x W(z) e maximum 9
-1 x 100) for P < 0.5 l
over z 2.237# x K(z) )
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0.5
./
j 2.
Either of,the following actions shall be taken:
a.
Place the core in an equilibrium condition where the
. limit in 4.2.2.2.c is satisfied.
Power level may
'then be increased provided the AFD limits of Figure 3.2-1 are reduced 1% AFD for each percent F (z) exceeded its limit, or q
b.
Comply with the requirements of Specification 3.2.2 for F (z) exceeding its limit by tha percent calculated 0
above.
- See page 3/4 2-6a.
SEQUOYAH - UNIT 2 3/4 2-6 Amendment No. 21, 95
k POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) g.
The limits specified in 4.2.2.2.c, 4.2.2.2.e, and 4.2.2.2.f above are not applicable in the following core plane regions:
1.
Lower core region 0 to 15 percent inclusive.
2.
Upper core region 85.to 100 percent inclusive.
4.2.2.3 When F (z) is measured for reasons other than meeting the requirements q
of Specification 4.2.2.2 an overall measured F (z) shall be obtained from a q
power distribution map and increased by 3 percent to account for manufacturing tolerances for further increased by 5 percent to account for measurement uncertainty.
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- The limit shall be 2.15 instead of 2.237 until an analysis in conformance with 10 CFR 50.46, using plant operating conditions and showing that a limit of 2.237 satisfies the requirements of 10 CFR 50.46(b), has been completed and submitted to NRC.
SEQUOYAH - UNIT 2 3/4 2-6a Amendment No. 21, 95
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EMERGENCY CORE COOLING SYSTEMS jl SURVEILLANCE REQUIREMENTS (Continued) i b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the solution in the water-filled j
c.
At least once per 18 months by:
1.
Verifying that each accumulator isolation valve closes automa-tically when the water level in the water-filled accumulator is i
92.0 + 2.6/-5.8 inches above the tank vendor working line when corrected for the mass of cover gas.
2.
Verifying that the total dissolved nitrogen and air in the water-filled accumulator is less than 80 SCF per 1800 cubic feet of water (equivalent to 5 x 10 s pounds nitrogen per pounds water).
d.
At least once per 5 years by removing the membrane installed between the water-filled and nitrogen bearing accumulators and verifying that the removed membrane bursts at a differential pressure of 40 + 10 psi.
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l SEQUOYAH - UNIT 2 3/4 5-4 Amendment No. 17, 95 l