ML20195G310
| ML20195G310 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/17/1998 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20195G316 | List: |
| References | |
| NUDOCS 9811200254 | |
| Download: ML20195G310 (16) | |
Text
.
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t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
4 WASHINGTON, D.C. 20056 4001
'+9.....,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 237 License No. DPR-77 9
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 26,1998, 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 corc. mon 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.
9811200254 981117 PDR ADOCK 05000327 P
d 9 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attach' ment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 237 aro 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, to be implemented no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdo.), Director Project Directorate ll-3
- Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: tbwrber 17, 1998
's ATTACHMENT TO LICENSE AMENDMENT NOJ7 FACILITY OPERATING LICENSE NO. DPR-77 J
l DOCKET NO. 50-327 f
j.
Revise the Appendix A Technical Specifications by removing the pages identified below and l
inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginallines indicating the area of change.
REMOVE INSERT 3/4 4-19 3/4 4-19 3/4 4-21 3/4 4-21 3/4 4-22 3/4 4-22 B 3/4 4-4a B 3/4 4-4a B 3/4 4-5 B 3/4 4-5 I
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3/4.4,8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the pYimary coolant shall be limited tos l
a.
Less than or equal to 0.35 microcuries/ gram DOSE EQUIVALENT I-131,'
l and b.
Less than or equal to 100/5 microcuries/ gram.
APPLICABILITY: MODES 1, 2,
3, 4 and 5 ACTION:
MODES 1, 2 and 3*
a.
With the specific activity of the primary coolant greater than R121 0.35 microcuries/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> l
during one continuous time interval or exceeding the limit line shown on-Figure.3.4-1, be in at least HOT STANDBY with T less than 500'F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
avg i
b.
With the specific activity of the primary coolant greater than 100/E lR121 microcuries/ gram, be in at least JKME STANDBY with T less than ',
500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, avg.
l MODES 1, 2,
3, 4 and 5 a.
With the specific activity of the primary coolant greater than 0.35 microcuries/ gram DOSE EQUIVALENT I-131 or greater than 1007E l
microcuries/ gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.
R121
- With T,yg greater than or equal 500'F.
SEQUOYAH - UNIT 1 3/4 4-19 Amendment Nr
-36, 114 237
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TABLE 4.4-4 i
- r PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE t
.AND ANALYSIS PROGRAM
.L i
^
TirPE OF MEASUREMENT SAMPLE AND-ANALYSIS-MODES IN WHICH SAMPLE AND ANALYSIS FREOUENCY AND ANALYSIS REOUIRED 1.
Gross Activity. Determination At least once per,72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 1,. 2. - 3, 4 2.
Isotopic Analysis for DOSE EQUIVA-1 per 14 days 1
'I
-LENT I-131 Concentration l
3.
Radiochemical for E Determination.
I per 6 months
- 1 4.
Isotopic Analysis for Iodine a)
Once per.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, 1
,2 3
4 5
Including I-131, I-133, and I-135 whenever the specific activity exceeds 0.35 l
-i pCi/ gram DOSE EQUIVAL_ENT~I-131 or 100/E pCi/ gram, and
[
t b)
One sample between 1,
2, 3
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 percent of phe i
RATED THERMAL i
POWER within a one hour period.
i Until the specific activity of the primary coolant system is restored within its limits.
3 Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since the reactor was last suberitical for-48 hours or longer.
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20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT l 131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.35 Cl/ gram Dose Equivalent 1131 l
SEQUOYAH UNIT 1 3/4422 Amendnmt it. 737
4 l
e 3/4,4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection syste'ms required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure i
Boundary. Thes' detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Cooladt Pressure Boundary Leakage Detection Systems," May 1973.
3/4.4.6.2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM.
This threshold value is sufficiently low to ensure early detection of additional leakage.
The surveillance requirements for RCS Pressure Isolation Valves provide added assurances of valve integrity thereby reaucing the probability of gross valve failure and consequent intersystem LOCA.
Leakage from the RCS isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
The 10.GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.
The CONTROLLED LEAKAGE limitation restricts operation when the total flow supplied to the reactor coolant pump seals exceeds 40 GPM with the modulating valve in the supply line fully open at a nominal RCS pressure of 2235 psig.
This limitation ensures that in the event of a LOCA, the safety injection flow will not be less than assumed in the accident analyses.
The total steam generator tube leakage limit of 600 gallons per day for R226 all steam generators and 150 gallons per day for any one steam generator will minimize the potential for a significant leakage event during steam line break.
Based on the NDE uncertainties, bobbin coil voltage distribution and crack growth rate from the previous inspection, the expected leak rate following a steam line rupture is limited to below B.21 gpm at atmospheric conditions and 70*F in the faulted loop, which will limit the calculated offsite doses to within 10 percent of the 10 CFR 100 guidelines. If the projected and cycle distribution of crack indications results in primary-to-secondary leakage greater than 8.21 gpm in the faulted loop during a postulated steam line break additional tubes must be removed from service in order to reduce the
- event, postulated primary-to-secondary steam line break leakage to below 8.21 gpm.
The ISO-gallons per day limit incorporated into SR 4.4.6 is more restrictive than the standard operating leakage limit and is intended to provide an additional margin to accommodate a crack which might grow at a greater than expected rate or unexpectedly extend outside the thickness of the tube support plate. Hence, the reduced leakage limit, when combined with an effective leak rate monitoring program, provides additional assurance that, should a significant leak be experienced, it will be detected, and the plant shut down in a timely manner.
PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.
Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to l
be promptly placed in COLD SHUTDOWN.
R226 l
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SEQUOYAH - UNIT 1 B 3/4 4-4a Amendment No. 16, 189, -?t4, 222,P37 I
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REACTOR COOLANT SYSTEM BASES The surveillance requirements provide adequate assurance that concentra-tions in excess of the limits will be detected in sufficient time to take corrective action.
l 3 /4. 4. 8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appro-priately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.
The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific site parameters of the Sequoyah Nuclear Plant site, such as site boundary location and meteorological conditions, were not considered in this evaluation.
i The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than or equal to 0.35 microcuries/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER. Operation with specific activity levels exceeding 0.35 microcuries/ gram DOSE EQUIVALENT I-131 but within the limits shown on Figure 3.4-1 should be limited to no more than 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> per s
year since the activity levels allowed by Figure 3.4-1 increase the 2-hour R121 thyroid dose at the site boundary by a factor of up to 20 following a postulated steam generator tube rupture.
Reducing T, to less than 500'F prevents the release of activity should a steam generator tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action.
Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.
i SEQUOYAH - UNIT 1 B 3/4 4-5 Amendment No. 144, 237 i
p nnuru j[,
'4 UNITED STATE 8 j
NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 30000-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. ??7 License No. DPR 79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 26,1998, 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 l
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.
L l
~-
4
, 2.
Accordingly, the licenge 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-79 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 227
, 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, to be implemented no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION y
Frederick J. Hebdorv, Director Project Directorate 11-3
- Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
Noveter 17, 1998 i
m.
ATTACHMENT TO LICENSEJMENDMENT NO.??7 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 l
Revise the Appendix A Technical Specifications by removing the pages identified below and l
inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT
'3/4 4-24 3/4 4 3/4 4-26 3/4 4-26 3/4 4-27 3/4 4-27 B 3/4 4 4 B 3/4 44 I
B 3/4 4-5 8 3/4 4-5 i
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' a REACTOR COOLANT SYSTEM' 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION i
-3 4.8 The specific activity of the primary coolant shall be limited to:
a.
Less than or, equal to 0.35 microcurie per gram DOSE EQUIVALENT I-131, l
and j
b.
Less than or equal to 100/5 microcuries per gram.
APPLICABILITY: MODES 1 2,
3, 4 and 5 ACTION:
MODES 1,.2 and 3*:
lR107 a.
, With the specific activity of the primary coolant greater than 0.35 microcurie per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> l
I during one continuous time interval or exceeding the limit line shown 4
on' Figure 3.4-1, be in at least HOT STNTDBY with T less than 500*F m
within 6. hours.
i
'b.
With the specific activity of the primary coolant greater than 100/5 lR107
' microcurie per gram,'be in at least HOT STANDBY with T less than y
500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 1, 2,
3, 4 and 5:
a With the specific activity of the primary coolant greater than 0.35 l
microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.
R107 i
- With Tn greater than or equal to 500*F.
SEQUOYAH - UNIT 2 3/4 4-24 Amendment No. 26,-1-07,727 1
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.y TABLE 4.4-4 PRIMA?! -ELANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM
+
- TYPE OF MEASUREMENT.-
SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE--
_ WD ANALYSIS FREOUENCY s
AND ANALYSIS REOUIRED 1.
Gross Activity Determination At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- 1. - 2, 3
.4 2.
. Isotopic Analysis for-DOSE EQUIVA-1.per 14 days 1
LENT I-131 Concentration 3.
Radiochemical for E Determination 1 per 6 months
- 1 F
4.
Isotopic Analysis for Iodine a) Once per.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, 1*, 2",
3 4*,
5 Including I-131, I-133, and I-135 whenever the specific activity exceeds 0.35 l
pCi/ gram DOSE EQUIVALENT I-131 or.100/E pCi/ gram, and' b) One sample between 1,
2, 3
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 exceedinIg 15 percent of the RATED THERMAL POWER within a one hour period.
3Until the specific activity of the primary coolant system'is restored within its limits.
4 Sample to be taken after a. minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed 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.
SEQUO'fAH - UNIT 2 3/4 4-26 W
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. _ m 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT l 131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.35 Ci/ gram Dose Equivalent 1131 l
SEOIJOYAH - UNIT 2 3/4 4-27 W t W. 227
o o.
REACTOR COOLANT SYSTEM BASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKA2E 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.
3/4.4.6.2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM.
This threshold value is sufficiently low to ensure early detection of addition 61 leakage.
The surveillance requirements for RCS Pressure Isolation Valves provide added assurances of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.
Leakage from the RCS isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
a The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.
The CONTROLLED LEAKAGE limitation restricts operation when the total flow supplied to the reactor coolant pump seals exceeds 40 GPM with the modulating valve in the supply line fully open at a nominal RCS pressure of 2235 psig.
This limitation ensures that in the event of a LOCA, the safety injection flow will not be less than assumed in the accident analyses.
The total steam generator tube leakage limit of 600 gallone per day for R213 all steam generators and 150 gallons per day for any one steaa generator will minimize the potential for a significant leakage event during steam line break.
Based on the NDE uncertainties, bobbin coil voltage distribution and crack giowth rate from the previous inspection, the expected leak rate following a steam line rupture is limited to below 8.21 gpm at atmospheric conditions and 70 'F in the faulted loop, which will limit the calculated offsite doses to within 10 percent of the 10 CFR 100 guidelines.
If the projected and cycle distribution of crack indications results in primary-to-secondary leakage greater than 8.21 gpm in the faulted loop during a postulated steam line break event, additional tubes must be removed from service in order to reduce the postulated primary-to-secondary steam line break leakage to below 8.21 gpm.
The 150-gallons per day limit incorporated into SR 4.4.6 is me.e rertrictive than the standard operating leakage limit and is intended to provide an additional margin to accommodate a crack which might grow at a greater than expected rate or unexpectedly extend outside the thickness of the tube support plate. Hence, the reduced leakage limit, when combined with an effective leak rate monitoring program, provides additional assurance that, should a significant leak be experienced, it will be detected, and the plant shut down in a timely manner PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.
Therefore, the presence of any PRESSURE BCUNDARY LEAKAGE requires tne unit to be promptly placed in COLD SHUTDOWN.
lR213 SEQUOYAH - UNIT 2 B 3/4 4-4 Amendment No. 211, 213,777
e
.o REACTOR COOLANT SYSTEM BASES 3 /4. 4. 7 CHEMISTRY The limitations on Reactor Cool' ant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent. Corrosion stuuies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concen-trations to within the Steady State Limits.
The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.
3 /4. 4. 8 SPECIFIC ACTIVITY 1
The limitations on the specific activity of the primary coolant ensure that the resulting 2-hour doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.
The values for the limits on specific activity represent limits based upon a parametric evaluation by the NRC of typical sit? locations. These values are conservative in that specific site parameters of the Sequoyah site, such as site boundary. location and meteorological conditions, were not considered in this evaluation.
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.35 l
microcuries/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER. Operation with specific activity levels exceeding 0.35 microcuries/ gram DOSE EQUIVALENT I-131 but within the limith l
shown on Figure 3.4-1 should be limited to no more than 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> per year since the activity levels allowed by Figure 3.4-1 increase the 2-hour thyroid R107 i
- me at the site boundary by a factor of up to 20 following a postulated steam
)
generator tube rupture.
1 l
l SEQUOYAH - UNIT 2 B 3/4 4-5 Amendment No. 1C.7. ??7