ML20095F274
| ML20095F274 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/13/1995 |
| From: | Matthews D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20095F278 | List: |
| References | |
| NUDOCS 9512180359 | |
| Download: ML20095F274 (13) | |
Text
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION 4
WASHINGTON, D.C. 30e06 0001 s.,.....,f CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-325 e
BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 180 j
License No. DPR-71 j
1 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light l
i Company (the licensee), dated October 23, 1995, 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 (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 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 2.C.(2) of Facility Operating License No.
DPR-71 is hereby amended to read as follows:
9512190359 951213 ADOCK0500g4 DR
i
- 4
)
i (2)
Technical Specifications i
The Technical Specifications contained in Aqmndices A and B, as revised through Amendment No.180, 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 j
shall be implemented within 60 days of issuance, j
FOR THE NUCLEAR REGULATORY COMISSION i
M
- 1 David B. Matthews, Director V
Project Directorate II-l Division of Reactor Projects - I/II I
Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications l
Date of Issuance: December 13, 1995 4
j i
t i
l 1
l
ATTACHMENT TO LICENSE AMENDMENT NO.180 FACILITY OPERATING LICENSE NO. OPR-71 DOCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 3/4 4-7 3/4 4-7 3/4 4-9 3/4 4-9 1
B 3/4 4-3 B 3/4 4-3 B 3/4 4-4 8 3/4 4-4 i
i
REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.4 The chemistry of the reactor coolant system shall be maintained within the. limits specified in Table 3.4.4-1.
APPLICABILITY: OPERATIONAL CONDITIONS 1. 2.'3. 4. and 5*.
i ACTION:
a.
In OPERATIONAL CONDITIONS 1. 2. and 3:
1 1.
With the conductivity or chloride concentration exceeding the limits specified in Table 3.4.4-1. but less than 10 vmho/cm at 25 C and less than 0.5 ppm. respectively, operation may continue for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and this condition need not be reported to the Commission provided that operation under these conditions shell not exceed 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year. The provisions of Specification 3.0.4 are not applicable.
2.
With the conductivity or chloride concentration exceeding the limits specified in Table 3.4.4-1 for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during one continuous time interval or with the conductivity exceeding 10 pmho/cm at 25 C or chloride exceeding 0.5 ppm.
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 OPERATION CONDITIONS 4 and 5* with the conductivity and/or I
chloride concentration of the reactor coolant in excess of the limit specified in Table 3.4.4-1. restore the conductivity and/or chloride concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
l'
- Exce t during planned chemical decontamination activities (with the reactor vesse defueled).
BRUNSWICK - UNIT 1 3/4 4-7 Amendment No.180 l
TABLE 3.4.4-1 REACTOR CODLANT SYSTEM CHEMISTRY LIMITS OPERATIONAL CONDITION CHLORIDES CONDUCTIVITY (umhos/cm 9 25'C) 1
< 0.5 ppm
< 2.0 2
< 0.2 ppm
< 2.0
- 3. 4. and 5*
< 0.2 ppm
<10.0 I
l
- Except during planned chemical decontamination activities (with the reactor vessel defueled).
BRUNSWICK - UNIT 1 3/4 4-9 Amendment No.180 1
sn REACTOR COOLANT SYSTEM BASES The surveillance requirements provide adecuate assurance that concentrations in excess of the limits will be cetected in sufficient time to take corrective action.
In order to reduce personnel radiation exposure, chemical decontamination of portions of the reactor coolant system may be performed during shutdown. During the chemical decontamination process, the injection of chemical solvents may cause the reactor coolant system conductivity and chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination process are selected and evaluated to ensure their chemical reactivity will not adversely impact components or the structural integrity of the reactor coolant system.
Because decontamination activities are performed at temperatures significantly less than normal operating temperatures, the chemical reactivity of these solvents will not increase the likelihood of stress corrosion occurring nor i
affect those stress corrosion cracks that may already be present.
~
3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2-hour thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines in 10CFR 100. Permitting operation to continue for limited time periods with higher specific activity levels accomodates short-term iodine spikes which may be associated with power level changes, and is based on the fact that a steam line failure during these short time periods is considerably less likely. Operation at the higher activity levels, therefore, is restricted to a small fraction of the unit's total operating time. The upper limit of coolant iodine concentration during short-term iodine spikes ensures that the thyroid dose from a steam line failure will not exceed 10 CFR Part 100 dose guidelines.
Information obtained on iodine spiking will be used to assess the parameters associated with spiking ahenon.ana. A reduction in frequency of isotopic analysis following power c1anges may be permissible, if justified by the data obtained.
Closing the main steam line isolation valves prevents the release of activity to the environs should the steam line rupture occur. The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.
3/4.4.6 PRESSURE / TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.
i These cyclic loads are introduced by normal load transients, reactor trips, and start-up and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 4.2 of the FSAR. During BRUNSWICK - UNIT 1 B 3/4 4-3 Amendment No.180 l
~
REACTOR COOLANT SYSTEM BASES PRESSURE /TEMPERAllJRE LIMIH (Continued) start-up and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.
During heatu). the thermal gradients in the reactor vessel wall produce thermal stresses w1ich vary from compressive at the inner wall to tensile at the outer wall. Thermal-induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure. During cooldo m thermal gradients to be accounted for are tensile at the inner wall and compressive at the outer wall.
The reactor vessel materials have been tested to determine their initial RT,.
The results of these tests are shown in GE NEDO 24161. Reactor operation and resultant fast neutron. E>l Mev. fluence will cause an increase in the RT Therefore, an adjusted reference temperature, based upon the fluence, m.can be predicted using the proper revision of Regulatory Guide 1.99.
The pressure-temperature limit curve Figures 3.4.6.1-1, 3.4.6.1-2 and 3.4.6.1-3a through 3.4.6.1-3c include predicted adjustments for this shift in at the end of indicated EFPY. as well as adjustments to account for the RT, tion of the pressure-sensing instruments.
loca The actual shift in RT of the vessel material will be checked periodically during operatio,n by removing and evaluating. in accordance with ASTM E185-82. reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area. Since the neutron spectra at the irradiation samples and vessel inside radius vary little, the measured transition shift for a sample can be adjusted with confidence to the adjacent section of the reactor vessel.
The pressure-temperature limit lines shown in Figures 3.4.6.1-1, 3.4.6.1-2 and 3.4.6.1-3a through 3.4.6.)-3c have been provided to assure compliance with the minimum temperature requirements of the 1983 revision to Appendix G of 10CFR50. The conservative method of the Standard Review Plan has been used for heatup and cooldown.
The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided in Table 4.4.6.1.3-1 to assure compliance with the requirements of ASTM E185-82.
BRUNSWICK - UNIT 1 B 3/4 4-4 Amendment No. 180 l
pun UNITED STATES p
j
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 2066M001 CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 211 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated October 23, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) nd the Commission's rules and regulations set j
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 1
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 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 amendraent 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 i
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)
Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 211. are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in ace l?ance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and 4
shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMISSION M
C N/
David B. Matthews, Director Project Directorate II-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 13, 1995 t
.m
.3.
ATTACHMENT TO LICENSE AMENDMENT NO. 211 FACILITY OPERATING LICENSE NO. Di'R-62 DOCKET NO. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 3/4 4-7 3/4 4-7 3/4 4-9 3/4 4-9 B 3/4 4-3 B 3/4 4-3 8 3/4 4-4 8 3/4 4-4
)
i I
.7
(
j 3/4.4.4 ~ CHEMISTRY t
LIMITING CONDITION FOR OPERATION j
3.4.4 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.
APPLICABILITY: OPERATIONAL CONDITIONS 1. 2. 3. 4 and 5*.
I ACTION.
a.
In OPERATIONAL CONDITIONS 1. 2. and 3:
l l
1.
With the conductivity or chloride cc.%entration exceeding the limits specified in Table 3.4.4-1 but less than 10 pmho/cm at 25'C and less than 0.5 ppm. respectively, operation may continue for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and this condition need not be reported to the Commission provided that operation under these conditions shall not exceed 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> i'
l per year. The provisions of Specification 3.0.4 are not applicable.
2.
With the conductivity or chloride concentration exceeding the limits specified in Table 3.4.4-1 for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during one continuous time interval or with the conductivity exceeding 10 pmho/cm at 25 C or chloride excseding 0.5 ppm.
r 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 l
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 CONDITIONS 4 and 5* with the conductivity and/or i
chloride concentration of the reactor coolant in excess of the l
(
limit specified in Table 3.4.4-1. restore the conductivity and/or chloride concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
j l
I
)
I L
i l
- Except during planned chemical decontamination activities (with the reactor vessel defueled).
4 7
BRUNSWICK - UNIT 2 3/4 4-7 Amendment No. 211 l
...-._. _ _ _.. - _ _.. _ _ m._...... _._
l TABLE 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY ', E l
l.
i OPERATIONAL' CONDITION CHLORIDES CONDUCTIVIT/ (umhos/cm 9 25*C) l i
1
< 0.5 ppm
< 2.0 l
2
< 0.2 ppm
< 2.0 i
- 3. 4. and 5*
< 0.2 ppm
<10.0 I
I l
i
- Except during planned chemical decontamination activities (with the reactor vessel defueled).
I BRUNSWICK - UNIT 2 3/4 4-9 Amendment No. 211 l
REACTOR COOLANT SYSTEM BASES The surveillance requirements provide adecuate assurance that concentrations in excess of the limits will be cetected in sufficient time to take corrective action.
In order to reduce personnel radiation exposure, chemical -
decontamination of portions of the reactor coolant system may be performed during shutdown. During the chemical decontamination process, the injection of chemical solvents may cause the reactor coolant system conductivity and chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination process are selected and evaluated to ensure their chemical reactivity will not adversely impact components or the structural integrity of the reactor coolant system.
Because decontamination activities are performed at temperatures significantly less than normal operating temperatures, the chemical reactivity of these solvents will not increase the likelihood of stress corrosion occurring nor affect those stress corrosion cracks that may already be present.
3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2-hour thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines in 10CFR 100. Permitting operation to continue for limited time periods with higher specific activity levels accommodates short-term iodine spikes which may be associated with power level changes, and is based on the fact that a steam line failure during these short time periods is considerably less likely.
Operation at the higher activity levels, therefore, is restricted to a small fraction of the unit's total operating time. The upper limit of coolant iodine concentration during short-term iodine spikes ensures that the thyriod dose from a steam line failure will not exceed 10 CFR.rt 100 dose guidelines.
Information obtained on iodine spiking will be used to assess the parameters associated with spiking )henomena. A reduction in frecuency of isotopic analysis following power clanges may be permissible. if ltustified by the data obtained.
Closing the main steam line isolation valves prevents tho r6 ease of activity to the environs should the steam line rupture occur. Tne surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.
3/4.4.6 PRESSURE / TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.
These cyclic loads are introduced by normal load transients, reactor trips, and start-up and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 4.2 of the FSAR.
During BRUNSWICK - UNIT 2 B 3/4 4-3 Amendment No. 211 1
3 j
-i l
PRESSURE / TEMPERATURE LIMITS (Continued)
E h ges are
_ start-up and shutdown, the rates of temperature and pressu l
with the design assumptions and satisfy"the stress limits-for cyclic l
operation.
the thermal gradients in the reactor vessel wall produce from compressive at the inner wall to tensile at j
During heatu),
thermal stresses w11ch va induced compressive stresses tend to alleviate the i
l the outer wall. Thermall tensile stresses induced the internal pressure. - During cooldown, thermal gradients to be accounted for are tensile at the inner wall and compressiv i
the outer wall.
The reactor vessel matarials have been tested to determine t Reactor i
The results of these tests are shown in GE NEDO 24161.
l i
operation and resultant fast neutron. E>l Mev, fluence will cause i.n increas RT,.
l Therefore, an adjusted reference temperature, based upon the fluence, can be predicted using the proper revision of Regulatory Guide 1.99.
in the RT,.
-The pressure / temperature limit curves Figures 3.4.6.1-1, J.4.6.1-2, and i
3.4.6.1-3a through 3.4.6.1-3c include predicted adjustments for this shift in at the end of indicated EFPY, as well as adjustments to account for.the l
i RT, tion of the pressure-sensing instruments.
f l
loca The actual shift in RT, of the vessel material will be checkedin accordance witi 1
periodically during operation by removing and evaluating, lance specimens f
ASTM E185-82, reactor vessel material irradiation surveil j
Since installed near the inside wall of the reactor vessel in the core area.
the neutron spectra at the irradiation samples and vessel inside radius vary L
little, the measured transition shift for a sample can be adjusted with l
confidence to the adjacent section of the reactor vessel.
F
.l l'
3.4.6.1-1, 3.4.6.1-2,
~ The pressure / tem>erature limit lines shown in Figures l
4 and 3.4.6.1-3a tirough 3.4.6.1-3c have been provided to assure complianc l
the minimum temperature requirements of the 1983 revi las been used l
4 f
j for heatup and cooldown.
' The number of reactor vessel irradiation surveillance specimens and the t
frequencies for removing and testing these specimens are prov i
i Table 4.4.6.1.3-1
}
I B 3/4 4-4 Amendment No. 211 1-1 BRUNSWICK - UNIT 2 1
i
.