ML20216D613
| ML20216D613 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/28/1997 |
| From: | Edison G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216D616 | List: |
| References | |
| NUDOCS 9709090373 | |
| Download: ML20216D613 (10) | |
Text
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$Y" k k
,y UNITE] STATES j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3000He01
- ...+
CAROLINA POWF(LA LIGHT COMPANY. et al.
DOCKET NO. 50 325 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 186 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated January 15, 1997, as supplemented on August 22. 1997. 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, the provisions of the Act, and the rules and regulations of the Comission:
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 Comission's regulations:
D.
The _ issuance of this 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.
DPR-71 is hereby amended to read as follows:
9709090373 970828 PDR ADOCK 05000324 P
Pm
.p.
(2)
Iechnical Soecifications The Technical Specifications contained in A)pendices A and B. as revised through Amendment No.186. are here)y incorporated in the license.
Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
(
bA Gordon Edison. Acting Director Froject Directorate Il-1 Division of Reactor Projects - 1/11 Office of Nuclear Reacter Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 28, 1997
?
f
ATTACHMENT TO LICENSE AMENDMENT NO.186 l
FACILITY OPERATING LICENSE NO. DPR-71 l
l DOCKET NO. 50-325 Replace the following ) ages of the Appendix A Technical Specifications with the enclosed pages. T1e revised areas are indicated by marginal lines.
Remove Paaes Jnsert Paoes 3/4 6 9 3/4 6 9 B3/4 6-3 B3/4 6-3
CONTA1 4 ENT SYSTEMS jf4.6.2 DEPRESSURIZATION SYSTEMS SUPPRESSION CHAM 8ER LINITING CONDITION FOR OPERATION 3.6.2.1 The suppression chamber shall be OPERABLE with:
a.
The pool water:
1.
Volume between 86,545 ft' and 89,843 fts, equivalent to a l
1evel between 27 inches and 31 inches, and a 2.
Maximum average temperature of 95'F during OPERATIONAL CONDITION 1 or 2, except that the maximum average temperature may be permitted to increase tot i
a) 105'F during testing which adds heat to the suppression chamber, b) llo'F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.
c) 120'F with the main steam line isolation valves closed following a scram, b.
Two OPERABLE suppression chamber water temperature instrumentation channels with a minimum of 11 operable RTD inputs per channel, c.
A total leakage from the drywell to the suppression chamber of less than the equivalent leakage through a 1 inch diameter orifice at a differential pressure of 1 psig.
APPLICABillTY: OPERATIONAL CONDITIONS 1, 2 and 3.
^
I ACTION:
With the suppression chamber water level outside the above limits, a.
restore the water level to within the limits within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
In OPERATIONAL CONDITION 1 or 2 with the suppression chamber average water temperature greater than 95'F, restore the average temperature t. less than or equal to 95'F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, except, as permitted above:
BRUNSWICK - UNIT 1 3/4 6 9 Amendment No.186 l l
l j
.,(DNTAINMENTSYSTEMS i
BASES 3/4.6 2 DEPRESSURIZATION AND COOLING SYSTEMS The specifications of this section ensure that the primary containment pressure will not exceed the calculated pressure of 49 psig during primary system blowdown from full operating pressure.
The pressure suppression pool water provides the heat sink for the reactor system. primary system energy release following a postulated rupture of the The pressure suppression chamber water volume must absorb the associated decay and structural sensible heat released during primary system blowdown from 1045 psig.
Since all of the gases in the drywell are purged i
into the pressure suppression chamber air space during a loss of coolant accident, the pressure of the liquid must not exceed 62 psig, the su)pression chamber maximum pressure.
The design volume of the suppression cham)er water and air, was obtained by considering that the total volume of reactor coolant to be condensed is discharged to the sup)ression chamber and that the drywell volume is purged to the suppression cham>er.
Using the minimum or maximum water volumes given in the specification, containment ressure during the design basis accident is approximately 49 psi of 89.g, whi h is below the design pressure of 62 psig.
Maximum water volume 843 ft resuljs in a downcomer submergence of 3'4" and the minimum volume of B6.545 ft results in a submergence approximately four inches less.
The Monticello tests were run with a submerged length of three feet and with complete condensation.
Thus, with respect to the downcomer submergence, this specification is adequate.
The maximum temperature at the end of the blowdown tested during the Humboldt Bay and Bodega Bay tests was 170'F. and this is conservatively taken to be the limit for complete condensation of the reactor coolant, although condensation would occur for temperatures above 170'F..
When it is necessary to make the suppression chamber inoperable, this shall'only be done as provided in Specification 3.5.3.3.
Under full power operation conditions, blowdown from an initial-suppression chamber water temperature of 90'F results in a water temperature of approximately 135*F 1mmediately following blowdown, which is below the temperature 170*F used for complete condensation.
At this temperature and atmospheric pressure, the available NPSH exceeds that required by both the RHR and core spray pumps:
thus, there is no dependenc overpressure during the accident-injection phase. y on containmentIf both RHR loo for containment cooling, there is no dependency on containment overpressure for post LOCA operations.
BRUNSWICK UNIT 1 8 3/4 6 3 Amendment No.186 l
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. seteHopt 49.....
CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. LINIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 217 License No. OPR 62 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated January 15. 1997, as supplemented on August 22, 1997, 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. the arovisions of the Act, and the rules and regulations of the Comission:
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 Comission's regulations:
D.
The issuance of this 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. DPR 62 is hereby amended to read as follows:
2 l
(2)
Technical Snecifications The Technical Specifications contained in A)pendices A and B, as 1
revised through Amendment No. 217. are here)y incorporated ir the I
license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Gordon Edison, Acting Director Project Directorate 11 1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuante:
August 28. 1997
l l-ATTACHMENT TO LICENSE AMENDMENT NO. 217 FAClllTY OPERATING LICENSE NO. DPR 62 DOCKET NO. 50 324 Replace the following sages of the Appendix A Technical Specifications with the enclosed pages. T1e revised areas are indicated by marginal lines.
Remove Paoes Insert Paoes 3/4 6 9 3/4 6-9 B3/4 6 3 B3/4 6-3 I
CONTAIMENT SVffEMS f
3/4.6.2-DEPRES$URIZATION SYSTEMS
- i 1}
$UPPRES$10N CHAMBER
- 4 lJ LIMITING CONDITION FOR OPERATION 3.6.2.1 The suppression chamber shall be OPERABLE with:
a.
The pool water:
1.
Volume between 86,545 ft* and 89,843 ft*, equivalent to a l
level between -27 inches and 31 inches, and a 2.
Maximum average temperature of 95'F uitng OPERATIONAL CONDITION 1 or 2, except that the maximum average temperature may be permitted to increase tot a) 105'F during testing which adds heat to the suppression chamber.
b) llo'F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.
c) 120'F with the main steam 1tne isolation vsives closed following a scram.
b.
Two OPERABLE suppression chamber water temperature instrumentation channels with a minimum of 11 operable RTD inputs per channel, A total leakage from the drywell to the suppression chamber of c.
less than the equivalent leakage through a 1-inch diameter ortftce at a differential pressure of 1 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
With the suppression chamber water level outside the above limits, a.
restore the water level to within the limits within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
In OPERAT10%L CONDITION 1 or 2 with the suppression chamber average water temperature greater than 95'F, restore the average temperature to less than or equal to 95'F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, except, as permitted above:
BRUNSWICK - UNIT 2 3/4 6-9 Amendment No. 217 I o
CONTAll0ENT SYSTDts 4ASES-l 3/4 6.2 DEPREstuRIZATION AND COOLING SYSTDts The specifications of this section ensure that the primary containment pressure will not exceed the calculated pressure of 49 psig during primary i
system blowdown from full operating pressure.
i The pressure suppression pool water provides the heat sink for the reactor primary system energy release following a postulated rupture of the system. The pressure suppression chamber water volume must absorb the i
associated decay and structural sensible heat released during primary system blowdown from 1020 psig.
into the Since all of the gases in the drywell are purged accident, pressure suppression chamber air space during a loss of coolantthe chamber maxtaus pressure.
The design volume of the suppression cham >er, water and air was obtained by considering that the total volume of reactor coolant to be co,ndensed is discharged to the suppression chamber and that the drywell i
l volume is purged to the, suppression chan>er.
-Using the minimum or maximum water volumes given in the specification.
containment pressure during the design basis accident is approximately 4g psig, whigh is below the design pressure of 62 :si of ag,643 ft results in a downconer submergence of 3p. Maximum water volume 4' and the minimum j
volume of 86,545 ft* results in a submergence approximately four inches less.
The Monticello tests were run with a submerged length of three feet and with complete condensation. Thus, with respect to the downconer submergence, this specification is adequate. The maximum temperature at the end of the blowdown test during the Humboldt Bay and Bodega Bay tests was 170'F, and this is conservatively taken to be the limit for complete condensation of the reactor coolant, although condensation would occur for temperatures above 170'F.
When it is necessary to make the suppression chamber inoperable, this shall only be done as provided in Specification 3.5.3.3.
Under full power operation conditions, blowdown from an initial suppression chamber water temperature of 90'F results in a water temperature of approximately 135'F immediately following blowdown, which is below the temperature 170'F used for complete condensation. At this temperature and atmospheric pressure and core spray pumps, the available NPSH exceeds that required by both the RHR
- thus, there is no dependenc overpressure during the accident injection phase. y on containment If both RHR loops are used for containment cooling, there is no dependency on containment overpressure for post-LOCA operations.
BRUNSWICK - UNIT 2 8 3/4 6-3 Amendment No. 217 I