ML20080C815
| ML20080C815 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/12/1994 |
| From: | Hansen A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080C818 | List: |
| References | |
| NUDOCS 9412200204 | |
| Download: ML20080C815 (14) | |
Text
m y.
.E
' hR N80p h
UNITED STATES
[
NUCLEAR REGULATORY COMMIS810N
~*
g WASHINGTON, D.C. 380BH001
- /
i j,
WISCONSIN ELECTRIC POWER COMPANY' F
L DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO.1 -
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 158 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated March 29, 1994, 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 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 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 3.B of Facility Operating License No.
DPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.158, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
~
9412200204 941212 PDR ADOCK 050002M 1
P PDR4 l
=
~
3 p.
y
' gs,:{,
.(
4 ieff 2,
[
13.
This license ~ amendment is' effective immediately upon issuance. The'
' Technical Specifications are to be implemented within 45 days from the-
'date of issuance. -
FOR THE NUCLEAR' REGULATORY COMMISSION L
g.
' Allen G.~ Hansen, Project' Manager Project Directorate III-3
. Division of Reactor Projects III/IV-Office of Nuclear Reactor Regulation 4 1
Attachment:
Changes to the Technical Specifications Date of issuance: ' December 12, 1994 P
)
i i
i e
I i
l
n macn:o9
- i
' UNITED STATE 8 j
j'
[
NUCLEAR REGULATORY COMMIS810N WASHINGTON. D.C. seteHem g.....,f WISCONSIN ELECTRIC POWER COMPANY DOCKET NO.'50-301 EQ1NT BEACH NUCLEAR PLANT. UNIT NO. 2 l
u AMENDMENT TO FACILITY OPERATING LICENSE F
Amendment No. 162 1.icense No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated March 29, 1994, complies with the standards and~
H recuirements of the Atomic Energy Act of 1954, as amended (the Act),
)
anc the Commission's rules and regulations set forth in'10 CFR.
j 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 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 3.8 of Facility Operating License No.
DPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.162, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
n o
(.,
i.L Vi This license amendment -is.' ffective 'immediately upon issuance.- 'The.
- 3.
e
- Technical Specifications are to be implemented within 45 days from the-date of issuance.-
FOR THE NUCLEAR REGULATORY COMMISSION 4
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects.III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: December 12, 1994 e
i f
f f
-r
.s.
A,,
8, i
I ATTACHMENT TO LICENSE' AMENDMENT NOS.158 AND 162
- l TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301
/
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT TS 15.3.2-1 through TS 15.3.2-1 through TS 15.3.2-5 (5 pages)
TS 15.3.2-4 (4 pages).
Table TS 15.3.2-1 (1 page)
Table TS 15.4.1-2 page 1 Table TS 15.4.1-2 page 1 through page 4 (4 pages) through page 4 (4 pages)
' I A
h
m 1
s L
15k3.24 CHEMICAL AND VOLUME CONTROL SYSTEM
/.
Anolicabilitv
-Applies to. operational status of the' chemical s'nd volume control system.
Ob.iective
~ To define those conditions of the chemical and volume control system necessary to' Linsure safe reactor operation.
Snecification A.
'When fuel is in the reactor, ~there shall.be at least one flow path to the core for boric acid injection..
B.
A reactor shall. not be taken critical unless the following chemical'and.
volume control system conditions are met:
1.
A minimum of two charging pumps for that reactor shall be. operable.
2.
System piping and valves shall be operable to the extent of-establishing two flow paths from the boric acid tank (s) and/or the refueling water storage tank to the reactor coolant system.
3.
If the boric acid tank (s) is required to comply with Specification B.2 above:
One boric acid transfer pump shall be operable per flow path a.
from the boric acid tank (s) with one of the BAST flow paths-lined up to supply boric acid to the applicable reactor, and b.
The boric acid concentration, minimum volume, 'and' solution temperature shall satisfy the requirements of Table 15.3.2-1.
C.
A second reactor shall not be taken critical with'one reactor already critical unless the following chemical and volume control system conditions are met:
1.
A minimum of two charging pumps for that reactor shall be' operable.
2.
System piping and valves shall be operable to the extent of establishing two flow paths from the boric acid tank (s) and/or the refueling water storage tank (s) to each reactor coolant system.
3.
If the boric acid tank (s) is required to comply with Specification C.2 above:
One boric acid transfer pump shall be operable per flow path a.
from the boric acid tank (s) with one of the BAST flow paths per unit lined up to supply boric acid to the applicable reactor, and b.
The boric acid concentration, minimum volume'and solution temperature shall satisfy the requirements of Table 15.3.2-1.
Unit 1 - Amendment No.18.158 15.3.2-1 Unit 2 - Amendment No.23,162
..3 Y
- Dh
~During' power operaticn,'the requirements of 15.3.2-B and C may be modified.
Lto. allow the following components to' be inoperable for a'specifled time.
If the' system is not restored to meet the requirements of 115.3.2-B or' C within the. time period specified, the appropriate reactor (s), except'as-s-
otherwise'noted, shall be placed in the hot shutdown' condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a shutdown margin equivalent of at least 1.05 delta k/k at-cold shutdown, no xenon conditions. ~If the requirements-of 15.3.2-B or C are not satisfied within an additional 7 days, the appropriate.
^
reactor (s)'shall be placed in the cold shutdown condition.within the next-30 hours.
- 1. -
One of the two operable charging pumps associated with an' operating reactor may be removed from service provided a charging pump associated with that. reactor is restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
2.
One of the two boron injection flow paths specified in B.2 or C.2 may be out of service provided two boron injection. flow paths are restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3.
One'of the boric acid transfer pumps designated in B.3'or C.3 may be out of service provided a boric acid transfer pump is~ restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Basis The chemical and volume control system provides control of the reactor coolant system boron inventory. This is normally accomplished by using one or more charging pumps in series with one of the two boric acid transfer pumps. Above cold shutdown conditions, a minimum of two boron injection flow paths are required per unit to insure functional capability in the event that an ' assumed single active failure renders one of the flow paths inoperable.: The boration volume available through any flow path is sufficient to provide the required shutdown margin at cold shutdown, xenon-free conditions from any expected operating condition. The maximum volume requirement is associated with boration from just critical, hot zero or full power, peak xenon with control rods at the insertion limit, to xenon-free, cold shutdown with the highest worth control rod assembly fully withdrawn. This requires approximately 24,100 gallons of 2000 ppm borated water from the refueling water storage tank (RWST) or the concentrations and volumes of borated water specified in Table 15.3.2-1 from the boric acid storage tanks (BASTS).
Unit 1 - Amendment No. 78,158 15.3.2-2 Unit 2 - Amendment No. 23,162 1
---n
+ee--,,
a,
~$
L A0ailable f. low paths from' the horated rater sources to.the charging pumps include,: but are not limited to', the' following:
g,
~1.
BASTS via one boric acid transfer pump through the normal makeup flow path to'the suction of the charging pumps.
2.
BASTS via one boric acid transfer pump through the emergency boration-flow path to the suction of the charging pumps.
3.
RWST..via gravity feed through the motor-operated valve to the suction-of the charging pumps.
- 4..
RWST via gravity feed through the manual valve to the suction of the charging pumps.
Availible flow paths from the charging pumps to the reactor coolant system include, but are not limited to, the following:
1)
Charging flow path to the RCS Loop A cold leg.
.1 2)
Charging flow path to the RCS Loop B cold leg.
3)
Seal injection flow path to the reactor coolant pumps.
t Boration of the RCS may also be accomplished via the two boric acid flow paths from the RWST and BASTS through the safety injection (SI) system. Use of these flow paths requires the RCS to be initially depressurized below the SI pump shutoff head.
The amount of boric acid injection must be sufficient to compensate for the-addition of positive reactivity from the decay of xenon after-a reactor trip from full power in order to maintain the required shutdown margin.. This can be accomplished through the operation of one charging pump taking suction from the RWST. Also, the time required for boric acid injection allows for the local alignment of manual valves to provide the necessary flow paths.
The quantity of boric acid specified in Table 15.3.2-1 for each concentration is the quantity necessary per-reactor relying on the BAST (s) as a borated water source to borate the reactor coolant to the required cold shutdown concentration at any time in core life. The volume requirements listed in Table 15.3.2-1 are based on the lower concentration in each range. The temperature limits specified Unit 1 - Amendment No.52.158 15.3.2-3 Unit 2 - Amendment No. 58,162
i in Table 15.3.2-1 are required to' maintain solution solubility at the upper l, - <
concentration.in each range. Heat tracing may be used to maintain solution' temperature -at or above the limits in Table 15.3.2-1.
If the solution temperature of either the flow path or the' BAST is not maintained at or above the-minimum temperature specified, the affected flow path must be declared inoperable and the appropriate' actions in Specification 15.3.2.D followed.
1 i
I i
I l
l l
l Unit 1 - Amendment No. 78,158 15.3.2-4 Unit 2 - Amendment No. 23,162 j
y 1
e Table 15.3.2-1
. Boric Acid Storage Tank (s):
Minimum Volume / Temperature / Concentration Boric Acid Soln MinimumCombig)d' Minimum T mperature Concentration (Wt%)
Volume (Gal.)
(*F) j 3.00 to <3.50 6860(3) 53.0 3.50 to <4.00 5870(3) 62.5 4.00 to <4.50 5120(3) 69.5 4.50 to <5.50 4550(3) 85.0 5.50 to <6.50 3700(3) 97.0 6.50 to <7.50 3150(3)
'107.0 7.50 to <8.50 2720(3) 116.0 8.50 to <9.50 2390 123.5 9.50 to <10.50 2140 131.0
~
10.50 to <!1.50 1930 138.0 11.50 to $12.50 1750 145.0 (1)
Per unit relying on BAST (s) as source of borated water.
(2)
Requires more than one BAST per unit.
(3)
Requires more than one BAST for two units combined.
Unit 1 - Amendment No.158
.. Unit 2 - Amendment No. 162 e
TABLE 15.4.1-2
. MINIMUM FREQUENCIES FOR EQUIPMENT AND SAMPLING TESTS i
i:,;
Igni Freauency
.l..
Reactor Coolant Samples
-Gross Beta-gamma 5/ week (7) g' activity (excluding tritium)
Tritium activity Monthly Radiochemical E.
' semiannually )"')
i Determination Isotopic Analysis for
.Every two weeks")
Dose Equivalent I-131 Concentration Isotopic Analysis for a.) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Iodine including I-131, whenever the specific I-133, and I-135 activity exceeds 1.0pC1/
i gram Dose Equivalen,t I-131 or 100/E pCi/ gram. )
b.) One sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following-a thermal power change exceeding 15% of. rated power in a one-hour.
period.
Chloride Concentration.
5/ week (8)
Diss. Oxygen Conc.
5/ week (')
Fluoride Conc.
Weekly 2.
Reactor Coolant Baron Boron Concentration Twice/ week 3.
Refueling Water Storage Boron Concentration Weekly (')
Tank Water Sample 4.
Boric Acid Tanks Boron Concentration Twice/ week and.after each BAST concentration change when they are being relied upon as a source of borated water.
5.
Spray Additive Tank NaOH Concentration Monthly 6.
Accumulator Boron Concentration Monthly Page 1 of 4 Ur.it 1 - Amendment No.#5.71.JS6.J27.J57.158 Unit 2 - Amendment No.33,76.199.133.76J.162
TABLE 15.4.1-2 (Continued)
Y Ital Frecuency Spent Fuel. Pit a) Boron Concentration Monthly..
7.
b) Water Level Weekly-Verification
~ 8.. ' Secondary Coolant Gross Beta-gamma Weekly
- Activity or gasusa-isotopic analysis Iodine concentration Weekly when gross Beta-ganusa activity equals or egoods 1.2 #1/cc 9.
.a) Rod drop times of)gli Each refueling or-full length rods after maintenance that could affect-
. proper functioning *.
b) Rodworth measurement Following each refueling shutdown prior to commencing power operation O
- 10. Control Rod Partial movement of Every 2 weeks all rods
- 11. Pressurizer Safety Valves Set point Every five~ years ""
- 12. Main Steam Safety Valves Set Point Every five years ""
- 13. Containment Isolation Trip Functioning Each refueling shutdown
- 14. Refueling System Interlocks Functioning Each refueling shutdown-
- 15. Service Water System Functioning Each refueling shutdown
- 16. Primary System Leakage Evaluate Monthly *
- 17. Diesel Fuel Supply Fuel inventory Daily
- 18. Turbine Stop and Governor Functioning Annually
- Valves
- 19. Low Pressure Turbige Visual and magnetic Every five years Rotor Inspection (
particle or liquid penetrant
- 20. Boric Acid System Storaga Tank and Daily ')
d piping temperatures 2 temperature required by Table 15.3.2-1 Page 2 of 4 Unit 1 - Amendment No.6A,65,7J,83,199.JD5,739,J55.J57,158 Unit 2 - Amendment No.69,79,76,87,193,199.J33 J59.J57,162
\\
' N.
7,
-]
TABLE'15.4.1-2-(Continued)'
l
- +.
J.asi Freauency h_
os)
. 21. PORV Block Valves.
- a. Complete Valve Cycle-Quarterly
- b. Open' position check-Every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
"')-
' 22. Integrity of Post Accident Evaluate
'Each refueling l
Recovery Systems Outside cycle Containment
- 23. Containment' Purge Supply.
Verify valves are Monthly l )
-l
- and Exhaust Iso ation Valves locked closed.
l
- 24. Reactor Trip Breakers -
- a. Verify independent-Monthly (')
l operability of automatic shunt and undervoltage trip-functions.
- b. Verify independent-Each refueling.
l operability of man-shutdown ual trip to shunt and undervoltage trip functions.
- 25. Reactor Trip Bypass
- a. Verify operability Prior to l'
a Breakers of the undervoltage breaker use l
trip function.
.i
- b. Verify operability-Each refueling-of the' shunt trip shutdown i
functions.
- c. Verify operability Each refueling of the manual trip shutdown to undervoltage trip functions.
26.120 VAC Vital Instr.
Verify Energizedor)
Shiftly.
l Bus Power 27.- Power Operated Relief Operate"
Each shutdownU53 l
Valves (PORVs).
PORV Solenoid Air Control Valves, and Air System Check
- 28. Atmospheric Steam Dumps Complete valve cycle Quarterly l
- 29. Crossover Steam Dump System Verify operability of Quarterly l
each steam dump valve.
.i Page 3 of 4 Unit 1 - Amendment No.64.65.77.83.199.J06.127. JAB.J55.757.158 Unit 2 - Amendment No.57.78.78.87.JB3.197.J33.752.157.151.162 4
w w
--we
=
a w
w r,
e
~---m---
< - - ~ -
v
-o+-r
---w
TABLE 15.4;1-2 (Continued)!~
~
~
~ ~ ~ ~
~
- 30. Pressurizer Heaters :
' Verify that.100KW ofa
- QuarterlyH l.
3 heaters'are available..
- L
{311. CVCS Charging Pumps,
' Verify grability of
. Quarterly-pumps.
4
- 32. Potential Dilution in?
Verify operability of:
Priortoplacingplant;l-Progress Alarm-alarm.
in cold shutdown.
i (1) Required only during periods of power operation.
(2).E deterinination will be started when the gross activity analysis of a
' filtered sample: indicates it10pci/cc and will be redetermined,1f the primary coolant gross radioactivity of a filtered sample increases by more than 10gCi/cc.
j (3) Drop' test" shall be conducted 'at rated reactor coolant flow.- Rods shall be-dropped under both cold and hot condition, but cold drop tests need not be timed.
t (4) Drop tests will be conducted in the hot condition' for rods on which maintenance was performed.
(5) As accessible without disassembly of rotor.
6 (6) Not required during periods of refueling shutdown.
'(7) At least once per week during periods of refueling shutdown.
(8) At least three times per week (with maximum time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between.
samples)-during periods of refueling shutdown.
(9) Not required during periods of cold or refueling shutdown, but must be performed '
prior to exceeding 200*F if it has not been performed during the previous.
t surveillance period.
(10) Sample to be taken after a minimum of 2 EFPD and 20 days power operation'since the reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
(11) An approximately equal number of valves shall be tested each ~ refueling outage i
such that all. valves will be tested within a five year period.
If any valve fails its tests, an additional number of valves equal to the number originally tested shall be tested.
If any 'of the additional tested valves fail. all remaining valves shall be tested.
(12) The specified buses shall be determined energized in the required manner at least once per shift by verifying correct static transfer switch alignment and indicated voltage on the buses.
(13) Not required if the block valve is shut to isolate a PORY that is inoperable for 1
reasons other than excessive seat leakage.
~
(14) Only applicable when the overpressure mitigation system is in service.
(15) Required to be performed only if conditions will be established, as defined in
' Specification 15.3.15, where the PORVs are used for' low teinperature' overpressure protection. The test must be performed prior to establishing these conditions.
(16) Test valve operation in accordance with the inservice test requirements of the.
ASME Boiler and Pressure Vessel Code,Section XI.
i (17) Operability of charging pumps is verified by ensuring that the pumps develop the -
required flowrate, as specified by the In-Service Test program.
(18) Not required to be performed if the reactor is'subcritical.
(19)RequiredonlywhentheBAST(s)arerelieduponasasourceofboratedwater.l Page 4 of 4 Unit 1 - Amendment No. 106.129.#8.J55.157.158 l
Unit 2 - Amendment No. 109.133.J52.159.J51.162
,-s l
b