ML20151B766
| ML20151B766 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/04/1988 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151B770 | List: |
| References | |
| NUDOCS 8804110236 | |
| Download: ML20151B766 (10) | |
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UNITED STATES E
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D, C. 20F5 i
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK SIEAM ELECTRIC PLANT, UNIT 1 i
, AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.117 License No. DPR-71 1
l 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated March 15, 1986 and December 17, 1987 complies I
with the standards and requirements of the Atomic Ent;rgy Act of 1
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 (i) that the activities authorized by this amendraent can be conducted without endangoring 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 comon defense and security or to the health and safety of the public; and I
E.
The issuance of this emendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements i
have been satisfied, l
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 j
hereby amended to read as follows:
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(2)TechnicalSpecifications The Technical Specifications contained in Appendices A and B, as l
revised through Amendment No.117, are hereby incorporated in the-license.
The licensee shall operate the facility in accordance with the Technical Specifications.
i 3.
This license amendment is effective as of the date of its issuance and i
shall be implemented within 60 days of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Divit hn of Reactor Projects I/II f
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Attachment:
j Changes to the Technical Specifications 4
Date of Issuance:
April 4, 1988 l
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l ATTACHMENT TO LICENSE AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO. OPR-71 DOCKET NO. 50-325 i
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
i Remove Pages Insert Psges j
i 3/4 4-13 3/4 4-13 l
3/4 4-17 3/4 4-17 l
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3/4.4.6 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITIlic CONDITION FOR OPERATION 3.4.6.1 The reactor vessel shell temperature and reactor vessel pressure shall be limited in accordance with the limit lines shown on (1) Figure 3.4.6.1-1 for heacup by non-nuclear means, cooldown following a nuclear shutdown, and low power PHYSICS TESTSI (2) Figure 3.4.6.1-2 for operations with a critical core other than low power PHYSICS TESTS or when the reactor vessel is ventedt and (3) Figure 3.4.6.1-3 for inservice hydrostatic or le d testing, withs A N ximum heatup of 100 F in any one-hour period, and a.
0 b.
A maximum cooldown of 100 F in any one-hour period.
APPLICABILITY: At all times.
ACTIONI With any of the soove limits exceeded, restore the temperature and/or pressure i
to within the limits within 30 minutest perform an engineering evaluation to determine the effects of the out-of-limit condition on the fracture toughness properties of the reactor coolant systems determine that the system remains acceptable for continued operations or be in at least Hot SHUTDOWN within 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 tlie next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIRENENTS 4.4.6.1.1 The reactor vessel shell temperature and reactor vessel pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.
I. 4.6.1.2 The reactor vessel shell temperature and reactor vessel pressure 1
shall be determined to be to the right of the criticality limit line of Figure 3.4.6.1-2 within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality.
4.4.6.1.3 The reactor material irradiation surveillance specimens shall be removed and examined to determine changes in material properties at the intervals shown in Table 4.4.6.1.3-1.
The results of these exa.ninations shall be sed to update Figures 3.4.6.1-1, 3.4.6.1-2, and 3.4.6.l-3.
The cumulative effective full power years shall be determined at least once per 18 months.
BRUNSWIC - UNIT 1 3/4 4-13 Amendment No.117 l
s TABLE 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM CAPSULE WITHDRAWAL SCHEDULE i
CAPSULE VESSEL WITHDRAWAL TIME (a)
NUMBER LOCAT!Otl (EFPY) 3 300*
8 2
120e (b) 1 30 (b)
(8) The specimen shall be withdrawn during refueling outage inmediately preceeding or following the specified withdrawal time.
(b) The schedule for removal of the second and third capsule shall be proposed after the results of the first capsule have been evaluated.
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BRUNSWICK - UNIT 1 3/4 4-17 Amendment No. 117
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY _CPERATING LICENSE Amendment No. 147 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated March 15, 1986 and December 17, 1987 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; P
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 publict 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 I
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.
r 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amenoment; and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:
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4 (2) Technical Specifications j
The Technical Specifications containea in Appendices A and B, as I
revised through Amendment No.147, are hereby incorporated in the license.
The licensee shall op
- ate ~ the facility in accordance with the Technical. Specifications.
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This license amendment is effective as of the date of'its issuance and l
l shall be implemented within 60 days of issuance, t
i FOR THE NUCLEAR REGULATORY COMMISSION l
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Elinor G. Adensam. Director t
Project Directorate 11-1 Division of Reactor Projects I/11
Attachment:
i' Changes to the Technical Specifications 6
Cate of Issuance: April 4, 1988 i
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ATTACHMENT TO LICENSE AMENDMENT NO.147 i
FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix A Technical Specifications witn the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 3/4 4-13 3/4 4-13 l
3/4 4-17 3/4 4-17 i
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TABLE 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROCRAM CAPSULE WITHDRAWAL SCHEDULE CAPSULE VESSEL WITHDRAWAL TIME (a)
NUMBER LOCATION (EFPY) 3 300' 10 2
120' (b) 1 3o.
(b)
I') The specimen shall be withdrawn during refueling outage immediately preceeding or following the specified withdrawal time.
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(b) The schedule for removal of the second and third capsule shall be proposed f
after the results of the first capsule have bson evaluated.
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BRUNSW1CK - UNIT 2 3/4 4-17 Amendment No. 147 P
REACTOR COOLANT SYSTEM 3/4.4.6 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITINU CONDITION FOR OPERATION 1
3.4.6.1 The reactor vessel shell temperatue and reactor vessel pressure shall be limited in accordance with the limit lines shown on (1.) Figure 3.4.6.1-1 for heatup by non-nuclear means, cooldown following a nuclear shutdown, and low power PHYSICS TESTSI (2) Figure 3.4.6.1-2 for operations with a critical core other than low power PHYSICS TESTS or when the reactor vessal is ventedt and (3) Figure 3.4.6.1-3 for inservice hydrostatic or leak testing, with:
A.
A maximum heatup of 100'F in any one-hour period, and b.
A maximum cooldown of 100'F in any one-hour period.
APPLICABILITY:
At all times.
l ACTIONI With any of the above limits exceeded, restore the temperature and/or pressura to within the limits within 30 minutest perform an engineering evaluation to determine the effects,f the out-of-limit condition on the fracture toughness properties of the casecor coolant systemi determine that the system remains acceptable for continued operations, or be in at least HOT SHUTDOVW within 12 l
hours and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.6.1.1 The reactor vessel shell temperature and reactor vessel pressure shall be determined to be within the limits at least once per 30 minutes during system hestup, cooldown, and inservice leak and hydrostatic testing operations.
4.4.6.1.2 The reactor vessel shell temperature and reacto vessel pressurn shall be determined to be to the right of the criticality limit line of Figure 3.4.6.1-2 within 15 minutes Frior to the withdrawat el cor. trol rods to bring the reactor to criticality.
4.4.6.1.3 The reactor material irradiation suceeillance specimens shall be cemovad and examined to determine changes in material properties at the L
intervals shown in Table 4.4.6.1.3-1.
The results ef these examinations shall I
be used to update Figures 3.4.6.1-1, 3.4.6.1-2, and 3.4.6.1.3.
The cumulative effective full power years shall be determined at least once per 18 months.
i BRUNSWICK - UNIT 2 3/4 4-13 Amendment No. 147