ML20199D831
| ML20199D831 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/14/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20199D836 | List: |
| References | |
| TAC-60289, TAC-60290, NUDOCS 8603240371 | |
| Download: ML20199D831 (12) | |
Text
'
h UNITED STATES
[
NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20555
%.....)
ALABAMA POWER COMPANY DOCKET NO. 50-348 i.
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO."1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. NPF-2 The Nuclear Regulatory Comission (the Commission) has found that: _
1.
A.
The application for amendment by Alabama Power Company (the licensee) dated November 27,- 1985, complies with 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, as amended, the provisions of the Act, and the regulations of the Comission; C..
There is reasonable assurance: (1) that the activities authorized by this amendment can be conductM 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 license amendment will not be inimical to the comon 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.
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-2 is hereby amended to read as follows:
r 8603240371 e60314 DR ADOCK 000 8
2
..,.y,,
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 61, 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.
FORtTHE N0. CLEAR REGULATORY COMMISSION qQ nm (edtd wO (s 3 1
Lester S.
enstein, Director PWR Project Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 14,1986 Yb O
6 e
e
4 ATTACHMENT TO LICENSE AMENDMENT NO. 61 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Revised Appendix A as follows:
Remove Pages Insert Pages 3/4 2-13 3/4 2-13 3/4 3-6 3/4 3-6 8 3/4 2-5 B 3/4 2-5
.e T4 e
o e
POWER DISTRIBUTION LIMITS ACTION:
(Continued) 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL : POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Tr.ip Setpoints to less than or equal to 55% of RATED THERMAL POWER wit'hin the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3.
Identify and correct the cause of the out of limit condition prior to increae.ing THERMAL POWER; subsequent POWER OPERATION above 50%
of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified at 95% or greater RATED THERMAL POWER.
d.
The provisions of Specification 3.0.4 are not applicable.
~
SORVEILLANC. REQUIREMENTS................
E
~
4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:
a.
Calculating the ratio at least once per 7 days when the alarm is OPERABLE.
b.
Calculating the ratio at least once per 12 h rs during steady state operation when the alarm is inoperable.
4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 75% of RATED THERMAL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normalized symmetric
"~
po'wei distribution, obtained from the two sets of four symmetric thimble locations or full-core flux map per Specification 3.3.3.2, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
FARLEY-UNIT 1 3/4 2-13 AMEN 0 MENT NO. 61
TABLE 3.3-1 (Continued)
TABLE NOTATION With the reactor trip system breakers in the closed position, tde control rod drive system capable of rod withdrawal.,and fuel in the reat. tor vessel.
The channel (s) associated with the protective functions derived from the out' of service Reactor Coolant Loop shall be placed in the tripped condition.
The provisions of Specification 3.0.4. are not applicable.
High voltage to detector may be de-energized above P-6.
Indication only.
The provisions of Specification 3.0.3 are not applicable if THERMAL POWER level > 10% of RATED THERMAL POWER.
ACTION STATEMENTS ACTION 1 - With the number of.0PERABLE channels one less than required by the Minimum Channels OPERABLE requirement, be in. HOT
- 9 NDBY within. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for u,' :o 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied; a.
The inoperable channel is placed in the tripped condition within I hour.
b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of the other channels per Specification 4.3.1.1.
c.
Either, THERMAL POWER is restricted to less than or equal to 75%
l of RATED THERMAL POWER.and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO from the i
remaining 3 detectors is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per l
Specification 4.2.4.2.
l L
l FARLEY - UNIT 1 3/4 3-6 AMENDMENT N0. 61 i
L
POWER DISTRIBUTION LIMITS BASES The radial peaking factor Fxy(Z), is measured periodically to provid,e additional assurance that the hot channel fgggor, FQ(Z), remains within its limit. The F xy limit for RATED THERMAL POWER (F
) as provided in the Radial Peaking Factor x
limitreportperSpecification6.$.1.11wasdeterminedfromexpected' power control maneuvers over the full range of burnup' conditions in the c6re.
3/4.2.4 -QUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assu,res that the radial power distribution satisfies the design values used in the p'ower capability analysis. Radial power distribution measurements are made during startup testing and periodically during power operation.
The limit'of 1.02, at which corrective action is required, provides DNB and -
linear heat generation rate protection with x-y plane power tilts.
The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned controi rod.
In the event such action does not correct the tilt, the margin for uncertainty on FQ is reinstated by reducing the maximum allowed power by 3 percent for each percent of ti';
' excess of 1.0.
For purposes of monitoring QUADRANT POWER TILT 010 when one excort etector is inoperable, the movable incore detectors are used to confirm that ti. normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO.
The incore detector monitoring is done with a full incore flux map or two sets of four synmetric thimbles. The two sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, E-5, E-11, H-3, H-13, L 5, L-11, N-8.
-m.
3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytic. ally demonstrated adequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation. The 18 month
' periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient ve'ification r
of flow rate on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis, r
FARLEY-UNIT 1 B 3/4 2-5 AMENDMENT NO. 61
r an o
UNITED STATES 8
},
NUCLEAR REGULATORY COMMISSION t
wAssincrow.o. c. rosss b
%, *.... o ALARANM POWER COMPANY DOCKET NO. 50-364 t.
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. NPF-8 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee) dated November 27, 1985, 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, as amended, the provisions of the Act, and the regulations of the
' Commission; C.-
There is reasonable assurance: (1) 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 ifcense 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 Pa.rt 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. NPF-8 is hereby amended to read as follows:
9
,--,--m
. (2)
Technical Specifications The Technical Specifications contained in Appendices.
A and B, as revised through Amendment No. 52, are
- hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effect'ive as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION -
b-a[d.
Le s te r S'.'
ubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: March 14,1986 9
r -
r i
^
I 1
- ATTACHMENT TO LICENSE AMENDMENT NO. 52 TO FACILITY OPERATING LICENSE NO. NPF-8 h
=
DOCKET NO. 50-364
~.
^
Revised. Appendix A as. follows:
4 Remove Pages Insert Pages 3/4 2-13 3/4 2-13 il
~
.3/4.3-6 3/4 3-6 i
8 3/4 2-5 B 3/4 2-5 5-1 1-
,,-='
7
-e-e e
O
POWER DISTRlBUTION LIMITS ACTION:
(Continued) 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High ~ Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />'.
~
3.
Identify and correct the cause of the out of limEt condition prior to ' increasing THERMAL POWER; subsequent POWER OPERATION above 50%
of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour-for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified at 95% or greater RATED THERMAL POWER.
- d.. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.2.4.1' The QUADRANT _ POWER TILT RATIO shall be determined to be within the 1.imit above 50% ot~ RATED THERMAL POWER by:
a.
Calculating the ratio at least once per 7 days when the alarm is OPERABLE.
b.
Calculating the ratio at least once. per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady sta operation when the alarm is inoperable.
4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 75% of RATED THERMAL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from the two sets of four symmetric thimble locations or full-core flux map per Specification 3.3.3.2, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
f i
1 I
FARLEY-UNIT 2 3/4 2-13 AMENDMENT NO. 52
TABLE 3.3-1 (Continued)
TABLE NOTATION With the reactor-trip system breakers in the closed position, the control rod drive system capable of rod withdrawal, and fuel in the readtor vessel.
The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.
The provisions of Specification 3.0.4 are not applicable.
High voltage to detector may be de-energized above P-6.
Indication only.
The provisions of Specification 3.0.3 are not applicable if THERMAL POWER level > 10% of RATED THERMAL POWER.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
_a.
The inoperable channel is placed in the tripped condition within I hour.
b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of the other channels per Specification 4.3.1.1.
c.
Either, THERMAL POWER is restricted to less than or equal to 75%
of RATED THERMAL POWER and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO from the remaining 3 detectors is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.
r FARLEY - UNIT 2 3/4 3-6 AMENDMENT NO. 52
r v
' POWER DISTRIBUTION LIMITS BASES The radial peaking factor Fxy(Z), is measured periodically to provide additional assurance that the hot channel fac or, F (Z), remains within its liinit. The F g
xy limit for RATED THERMAL POWER (FM ) as provided in the Radial Peaking Factor limit report per Specification 6.9.1.11 was determined from expecte'd power control maneuvers over the full range.of burnup conditions in the core.
3/4.2.4 QUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power' distribution measurements are made during startup testing and periodically during power operation.
The limit of 1.02, at which corrective action is required, provides DNB and _
linear heat generation rate protection with x-y plane power tilts.
The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod.
In the event such action does not correct the tilt, the margin for uncertainty on Fg is reinstated by reducing the maximum allowed power by 3 percent for each percent of tilt in excess of 1.0.
For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO.
The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles. The two sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, N-8.
3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated edequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits
- following load changes and other expected transient operation. The 18 month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of flow rate on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis.
r FARLEY-UNIT 2 B 3/4 2-5 AMENDMENT NV. 52