ML20153B486
| ML20153B486 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/11/1988 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20153B490 | List: |
| References | |
| GL-85-19, NUDOCS 8803220187 | |
| Download: ML20153B486 (26) | |
Text
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o, UNITED STATES NUCLEAR REGULATORY COMMISSION
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- e WASHINGTON D. C. 20555
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VIRGINIA ELECTRIC AND PONER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTW ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 1.icense No. NPF-4 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated June 1, 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 CFP Chapter I; B.
The facility will operate in con'ormity with the application, the provisinns of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (ii that the activities authorized b." this amendment can be ennducted without endargering 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 amandmant will not be inimical to the comen 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 regulatiers and all applicable requirements have been satisfied.
8803220187 080311 DR ADOCK 05000. 8
2 2.
Accordingly, the license is amended by chenges to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.0.f?) of Facility Operating License No. NPF-4 is hereby arended to read as follows:
(?) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No, 96, ara hereby incoroorated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 14 days of the date of its issuance.
F R THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Profects-I/II Office of Nuclear Reacter Reoulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
'1 arch 11, 1988
.J' ATTACPPENT TO LICENSF APENDMENT NO. og TO FACII.ITY OPERATING LICFNSE NO. NPF 4 DOCKET NO. 50-338 Replace the followina rages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identi'ied by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf paaes are also provided to mainteir document ernpleteness.
Paae 3/4 4-23 3/a a-23 B3/4 4-6 6-15 6-21 t'
TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS MINIMUM PARAMETER ANALYSIS FREQUENCIES DISSOLVED OXYGEN
- At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> CHLORIDE **
At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l
FLUORIDE **
At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l
- Not required with T,yg i 250'F
- Not required when the Reactor Coolant System is drained below the reactor pressure vessel nozzle and the internals and/or head are in place.
NORTH ANNA - UNIT 1 3/4 4-21 knendment No. 41
REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:
1.d uCi/ gram DOSE EQUIVALENT I-131, and l
a.
1 b.
1 100/T aci/ gram.
APPLICABILITY _: MODES 1, 2, 3, 4 and 5.
ACTION: Mr S 1, 2 and 3*
With the specific activity of the primary coolant > 1.0 uCi/ gram a.
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 /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T,yg < 500'F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With the specific activity of the primary coolant > 100/f uCi/ gram, be in at least HOT STANDBY with T
< 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
MODES 1, 2, 3, 4 and 5 With the specific activity of the primary coolant > 1.0 uCi/ gram a.
DOSE EQUIVALENT I-131 or > 100/E uCi/ 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, uNthT,yg greater than or equ&l to 500'F.
Amendment No. 96 ORm ANNA - UNIT 1 3/4 4-22
REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.
NORTH ANNA - UNIT 1 3/4 4-23 Amendment Ho, SE
TABLE 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE 5$
AND ANALYSIS PROGRAM E
TYPE OF MEASUREMENT SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE AND ANALYSIS FPTOUENCY ANALYSIS REQUIRED
- 1 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 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, andI 11:-5 whenever the specific activity exceeds 1.0 10 pCi/ gram DOSE EQUIVALENT I-131 j]
or 100/E pCi/ gram, and u
b) One sample between 1, 2, 3 2 & 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a THERMAL POWER
-l change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.
- ntil the specific activity of the primary coolant system is restored within its limits.
U 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.
I
BASES 3/4.4.7 CHEMISTRY The limitations on Reactor Coolant 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 in-The tegrity of the Reactor Coolant System over the life of the plant.
associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent. Corrosion studies show that opera-tion 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 struc-tural integrity of the Re:ctor Coolant System. The time interval per-mitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the con-taminant concentrations to within the Steady State Limits.
The surveillance requirements provide ad2quate assurance that con-centrations in excess of the limits will be detected in sufficient time to take corrective action.
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 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 The values for the limits on specific activity represent interim GPM.
limits band upon a parametric evaluation by the NRC of typical site These values are conservative in that specific site locations.
parameters of the North Anna site such as site boundary location and The meteorological conditions, were not considered in this evaluation.
NRC is finalizing site specific criteria which will be used as the basis for the reevaluation of the specific activity limits of this site.
This reevaluation may result in higher limits.
l l
l NORTH ANNA - UNIT 1 B 3/4 4-5 l
l
REACTOR COOLANT SYSTEM BASES The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity > 1.0 tCi/ 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.
Reducing T to < 500*F prevents the release of activity should a steam generator tube Mture 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.
3/4.4.9 PRESSURE / TEMPERATURE LIli!TS 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 startup and shutdown operations. The various catagories of load cycles used for design purposes are provided in Section 5.2 of the FSAR. During startup and shutdown, the rates of temperature and pressure changes are 1imited 50 that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.
During heatup, the thermal gradients
- the reactor vessel wall produce thermal stresses which vary from compressive at the inner wall to tensile at the outer wall. These thermal induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure. Therefore, a pressure-temperature curve based on steady state conditions (i.e., no thennal stresses) represents a lower bound of all similar curves for finite heatup rates when the inner wall of the vessel' is treated as the governing location.
NORTH AllNA - UNIT 1 B 3/4 4-6 Amendment No.96 f
f
AD:11NISTRATIVE CONTROLS ANNUAL REPORTSO 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to fiarch 1 of each year. The initial report shall be submitted prior to liarch 1 of tne year following initial criticality.
6.9.1.3 Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than LOO mrem /yr and their a accordingtoworkandjobfunctions,gociatedman-remexposuree.g., reactor operatio surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions, b.
The complete results of the steam generator tube inservice inspections performed during the report period (Reference Speci fication 4.4.5.5.b. ).
c.
The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
O A single submittal may be made for a multiple unit station.
T' s submittal should combine those sections that are comon to all units at the station.
O his tabulation supplements the requirements of 820.407 of 10 CFR Part 20.
T NORTH ANNA - UNIT 1 6-15 Amendment No. 5,96 m
I ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all cnailenges to the Reactor Coolant System PORVr or safety valves, shall be submitted on a monthly basis to the Director, Office of lianagement and Program Analysis, U. S. Nuclear Regulatory Comission, Washington, D. C. 20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.
i I
i NORTH ANNA - UNIT 1 6-16 Amendment No. 3, 5, 32, g,63 l
ADMINISTRATIVE CONTROLS (Continued)
_SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region II, within the time period specified for each re? ort.
These reports shall be submitted covering the activities identified below pursuant to the requirement of the applicable reference specification:
a.
Inservice Inspection Program Reviews shall be reported within 90 days of completion. Specification 4.0.5.
b.
ECCS Actuation shall be reported within 90 days of the occurrence.
The report shall describe the circumstances of the actuation and the total accumulated cycles to date.
Specifications 3.5.2 and 3.5.3.
c.
With Seismic Monitoring Instrumentation inoperable for more than 30 days, submit a special report within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrumentation to operable status.
Specification 3.3.3.3.
d.
For all seismic events actuating a seismic monitoring instrument, submit a special report within 10 days describing the magnitude, frequency spectrum and resultant effects upon features important to safety.
Specification 4.3.3.3.2.
e.
With Meteorological Instrumentation inoperable for more than 7 days, submit a special report within the next 10 days, outlining the cause of the malfunction and the plans for restoring the instrumentation to operable status. Specification 3.3.3.4.
f.
DELETED.
g.
With sealed source or fission dett:ctor leakage tests revealing the presence of > 0.005 microcuries of removable contamination submit a special repert on an annual basis outlining the corrective actions taken to prevent the spread of contamination.
Specifica-tion 4. 7.11.1.3.
0 h.
With the MTC more positive than 0 ak/k/ F submit a special report within the next 10 days describing the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
Specification 3.1.1.4.
NORTH ANNA - UNIT 1 6-21 Amendment No. 3, 48, U n %
4 H ACMlNISTRATIVE CONTROLS 1.
For any abnormal degradation of the structural integrity of the reactor vessel or the Reactor Coolant System pressure boundary detected during the performance of Specification 4.4.10, an initial report shall be submitted within 10 days after detection and a detailed report submitted within 90 days after the comple.
tion of Specification 4.4.10.
J.
For any abnormal degradation of the containment structure detected during the performance of Specification 4.6.1.6, an initial report shall be submitted within 10 days after completion of Specification 4.6.1.6.
A final report, which includes (1) a description of the condition of the liner plate and concrete. (2) inspection procedure, (3) the tolerance on cracking, and (4) the corrective actions taken, shall be submitted eithin 90 days after the completion of Specifi.
cation 4.6.1.6.
k.
Inoperable Fire Detection Instrumentation, Specification 3.3.3.7.
1.
Inoperable Fire Suppression Systems Specifications 3.7.14.1, 3.7.14.2, 3.7.14.3, 3.7.14.4 and 3.7.14.5.
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level, b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTABLE EVENTS and Special Reports.
l d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of changes made to Operating Procedures.
f.
Records of radioactive shipments.
g.
Records of sealed source leak tests and results.
h.
Records of annual physical inventory of all sealed source material of record.
i.
Records of the annual audit of the Station Emergency Plan and implementing procedures.
J.
Records of the annual audit of the Station Security Plan and implementation procedures.
6.10.2 The following records shall be retained for the duration of the IFacility Operating License:
NORTH ANNA - UNIT 1 6-22 Amendmentho.3,48,U73
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'4 1
NUCLEAR REGULATORY COMMISSION i
WASHINGTON. D. C. 20555
%...../
v!pGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NS. 50-339 NORTH ANNA POWER STATTON,IINIT NO. 2 AMEN 0 MENT TO FACILITV OPEPATING LICENSE
- Amendment No. 33 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Comissioni has #ound that:
A.
The application for amendment by Virgiria Electric and Power Company, et al., (the licensee) dated Jure 1, 1987, complies with the standards and requirenents of the Atomic Energv Act of 195a, 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 Comnission; C.
There is reasonable assurance (i) that the activities authori?.ed by this amendment can be conducted without endargering the health and safety of the public, and (iii 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 connor defense and security or to the health and safety of tha public:
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable recuirements have been satisfied.
i
.?.
2.
Accordingly, the license is amended by changes to the Technical Speci-fications es indicated in the attachment to this license amendment, and paraaraph 2.C.(2) of Facilitv Operating License No. NPF-7 is hereby amended to read as follows:
(2) Technical Speci#ications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 33
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 14 days of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate IT-?
Division nf Reactor Projects-l/II Office of Nuclear Reactor Reaulation
Attachment:
Charces to the Technical Specifications Date of Issuance:
March it,1938
ATTACHWENT TO LICENSE AMEirPFNT tl0 33 TO FACILITY OPF. RAT!NG LICENRE NO NPF 7 POCKET NO. 50-339 Replace the 'ollowing pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. Tha revised paqes are identified bv arendment number and contain vertical lires indicating the area o# changa.
The corresponding overleaf nages are also provided to raintain docurent completeress.
Page 3/4 4-2?
3/4 4-?3 R3/4 4-6 6-16 6-21 b
i
._,---..,_...,__-.,_,m___--m_.,
TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS MINIMUM PARAMETER ANALYSIS FREQUENCIES DISSOLVED OXYGEN" At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> CHLORIDE **
At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i
FLUORIDE **
At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i
" Not required with T,yg less than or equal to 250 F
- Not required when the Reactor Coolant System is drained below the reactor pressure vessel nozzle and the internals and/or head are in place.
NORTH ANNA - UNIT 2 3/4 4-21 Amenoment No. 51
9 REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.S The specific activity of the primary coolant shall be limited to:
Less than or equal to 1.0 uCi/ gram DOSE EQUIVALENT I-131, and a.
b.
Less than or equal to 100/T uCf/ gram.
APPLICABILITY,: MODES 1, 2, 3, 4 and 5.
ACTION: MODES 1, 2 and 3*
With the specific activity of the primary coolant greater than a.
1.0 uCi/ 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 /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T**9 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 />.
b.
With the specific activity of the primary coolant greater than 100/f uCi/ gram, be in at least HOT STANDBY with T less avg than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- With T,yg greater than or equal to 500*F.
NORTH ANNA - UNIT 2 3/4 4-22 Ainendment No. 33 l
j
r REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION ACTION:
(Continued)
MODES 1, 2, 3, 4'and 5 a.
With the specific activity of the primary. coolant greater than 1.0 uti/ gram DOSE EQUIVALENT I-131 or greater than 100/T pCi/ 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.
SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4 NORTH ANNA - UNIT 2 3/4 4-23 Amendment No. 83
TABLE 4.4-4 i
83 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE I
AND ANALYSIS PROGRAM I
TYPE OF MEASUREMENT SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE AIG ANALYSIS FREQUENCY ANALYSIS REQUIRED i
U 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 j
N 2.
Isotopic Analysis for DOSE I per 14 days 1
EQUIVALENT I-131 Concentration 3.
Radiochemical for E Determination 1 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,S Including I-131, I-133, and I-135 whenever the specific activity exceeds 1.0 pCi/ gram DOSE EQUIVALENT I-131 wA or 100/E pCi/ gram, and a
h 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 the RATED THERMAL POWER within a one l
hour period.
Until the specific activity of the primary coolant system is restored within its limits.
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 liours or longer.
~
b
\\
l REACTOR COOLANT SYSTEM BASES i
I l
3/4.4.7 CHEMISTRY The limitations on Reactor Coolant 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 insure 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 studies 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 con-centrations 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.
3/4.4.3 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 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 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 North Anna site such as site boundary location and meteorological conditions, were not considered in this evaluation.
The NRC is finalizing site specific criteria which will be used as the basis for the reevaluation of the specific activity limits of this site.
This reevaluation may result in higher limits.
NORTH ANNA - UNIT 2 8 3/4 4-5 v
w.
REACTOR COCLANT SYSTEM BASES The ACTION statement permitting POWER OPERAT10N to continue for 1imited tic'e periods with the primary coolant's specific activity greater than 1.0 uCi/ gram DOSE EQ'JIVALENT 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.
Reducing T to less than 500'F prevents the release of activity should asteangeneratN9 tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmo3pheric steam relief valves.
The surveillance requirements provide adequate assurance that excessive specific activity levels in the prins*y 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.
3/4.4.9 PRESSURE / TEMPERATURE LIMITS The temperature and pressure changes during heatup and cooldown are limited to be consistent with the requirements given in the ASME Boiler and Pressure Vessel Code,Section III. Appendix G.
- 1) The reactor coolant temperature and pressure and systen heatup and cooldown rates (with the exception of the pressurizer) shall be limited in acccrdance with Figures 3.4-2 and 3.4-3 for the first full-power service period.
NORTH ANNA - UNIT 2 B 3/4 4-6 Amendment No. 33
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AD:41NISTRATIVE CONTROLS 6.9.l.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details requested in license conditions based or other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 cays following resumption or commencement of commercial power operation, or (3) 9 months following initial If the Startup Report does not cover all criticality, w(hichever is earliest.
three events i.e., initial criticality, completion of stcrtuo test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL REPORTS 3/
6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted orior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their agsociated man-rem exposure according to work and job functions,t/ e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
1/
A single submittal may be made for a multiple unit station. The submittal should combine those sections that are connon to all units at the station.
2/
This tabulation supplements the requirements of 120.407 of 10 CFR Part 20.
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NORTH ANNA - UNIT 2 6-15 2
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ADMINISTRATIVE C054TROLS b.
The complete results of the steam generator tube inservice inspections performed during the report period (Reference Specification 4.4.5.5.b.),
The results of specific activity analysis in which the primary c.
coolant exceeded the limits of Specification 3.4.8.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 cor.ccritration and one othse radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the Reactor Coolant System PORVs or safety valves, shall be submitted on a monthly basis to the Director, Office of Management and Program Analysis U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th day of each month following the calendar month covered by the report.
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NORTH ANNA - UNIT 2 6-16 Amendment No. 37, 47, 83
ADMINISTRATIVE CONTROLS (Continued)
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region II, within the time period specified for each report.
These reports shall be submitted covering the activities identified below pursuant to the requirement of the applicable reference specification:
a.
Inservice Inspection Program Reviews shall be reported within 90 days of completion.
Specification 4.0.5.
b.
ECCS Actuation shAll be reported within 90 days of the occurrence.
The report shall describe the circumstances of the actuation and the total accumulated cycles to date.
Specifications 3.5.2 and 3.5.3.
c.
DELETED d.
With sealed sources or fission detector leakage tests revealing the presence of >0.005 microcuries of removable. contamination submit a special report on an annual basis out1Nng the corrective actions taken to prevent the 'pread of contamination. Specification 4.7.11.1.3.
0 e.
With the MTC more positive than 0 u/k/ F submit a special report within the next 10 days describing the valhe of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
Specification 3.1.1.4.
f.
For any abnonnal degradation of the structural integrity of the reactor vessel or the Reactor Coolant System pressure boundary detected during the performance of Specification 4.4.10.1, an initial report shall be submitted within 10 days after detection and a detailed report submitted within 90 days after the completion of Specification 4.4.10.1.
g.
For any abnonnal degradation of the containment structure detected during the performance of Speciff ;* *"n 4.6.1.6.2, an initial report shall be submitted within 10 days,
r completion of Specification 4.6.1.6.2.
A final report, which ii.,.ludes (1 a description of the conditionofthelinerplateandconcrete.(2))inspectionprocedure, (3) the tolerance on cracking and (4) the corrective actions taken, shall be submitted within 90 days after the completion of Specifica-tion 4.6.1.6.2.
h.
Inoperable Fire Detection Instrumentation, Specification 3.3.3.7, i.
Inoperable fire Suppression Systems Specifications 3.7.14.1, 3.7.14.2, 3.7.14.3, 3.7.14.4 and 3.7.14.5.
NORTH ANNA - UNIT 2 6-21 Amendment No. 31, gy, 33
g gists; uitvE CONTR0ls (Continued) 6.10 RECORD RETENTION _
In addition to the aoolicable record retention recuirements of Title 10, Cece of Federal Regulations, tne following records snall be retained for at least the minimum period indicated.
9.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level, b.
Records ar.d logs of principal C
. nee act4vities, inscections, repair and replacement of princi:-
nams of equipment related to nuclear safety, c.
All REPORTABLE EVENTS and Specia seports, d.
Records of surveillance activities, inspections and calibratiens required by these Technical Specifications, e.
Records of changes made to Operating Procedures.
f.
Records of radioactive shipments, g.
Records of sealed source leak tests and results.
n.
Records of annual physical inventory of all sealed source material of record.
1 Records of the annual audit of the Station Emergency Plan and implee.enting procedures.
J.
Recores of the annual audit of the Station Security Plan and implementing proceduros.
6.10.2 The following records shall be retained for the duration of the l
Facility Operating License:
1 a.
Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and essembly burnup histories, c.
Records of facility radiation and contamination surveys, d.
Records of radiation exposure for all individuals enterir? radiation control areas, e.
Records of gaseous and liquid ratitoactive material release to the envi rons, l
f.
Records of transient or operational cycles for those facility components identified in Table 5.7-1.
l NORTH ANNA - UNIT 2 6-22 Amendment No. 32,Al 67 l
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