ML20236S363
| ML20236S363 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/13/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20236S364 | List: |
| References | |
| DPR-65-A-121, TAC 65852, TAC 66116 NUDOCS 8711250104 | |
| Download: ML20236S363 (10) | |
Text
-
i h1,.
.![rasa UNITED STATES o,,
NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D. C. 20665
.j 5
l
%*..,+$
I NORTHEAST NUCLEAR ENERGY COMPANY i
THE CONNECTICUT LIGHT AND POWER COMPANY j
1 l
THE WESTERN MASSACHUSETTS ELECTRIC COMPANY j
DOCKET NO. 50-336 i
.M _ILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.121 l
License No. DPR-65 1
1 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The. applications for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated July 14, 1987 and September 4, 1987, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission;.
f C.
There is reasonable assurance (1) that the activities authorized by I
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; j
i 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 Conrnission's regulations and all applicable requirements have been satisfied, i
j 8711250104 371113 DR ADOCK 05000336 p
l 7
1 2.
- Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license. amendment, i
and paragraph 2.C.(2) of Facility Doerating License No. DPR-65 is hereby I
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised i
through Amendment No.121, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the j
Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
1 OR THE NUCL AR REG ATORY COMMISSION
)
M j
/'
k Jo F. Stolz, Dire to Pr fect Directorate 4
vision of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications i
Cate of Istuance: NOV 13 tm I
E i
i
)
l
______ _ ____ __ _ _ _ _ _ U
4 ATTACHMENT TO LICENSE AMENDMENT NO.121 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Apoendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Remove Insert 3/4 4-7a 3/4 4-7a 3/4 4-9 3/4 4-9 B3/4 4-2a B3/4 4-2a B3/4 4-3 B3/4 4-3
-~
..~....;._..
REACTOR COOLANT SYSTEM SURVEILL ANCE REQUIREMENTS (Continued) 4.4.5.1.4 Acceptance Criteria a.
As used in this Specification l.
Imperfection means an exception to the dimensions, finish or contour of a tube or sleeve from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube or sleeve wall thickness, if detectable, may be considered as imperfections.
o 2.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a g
tube or sleeve.
3.
Degraded Tube or sleeve means a tube or sleeve containing imperfections 3. 20% of the nominal wall thickness caused by degradation.
4.
% Degradation means the percentage of the tube wall or i
sleeve thickness affected or removed by degradation.
l 3.
Defect means an imperfection of such severity that it exceeds the plugging limit. A tucie containing a defect is defective.
6.
Plugging Limit means the imperfection depth at or beyond which the tube shall be repaired because it may become unserviceable prior to the next inspection and is equal to 40%
l of the nominal wall thickness for tubes or sleeves.
7.
Unserviceable describes the condition of a tube if it leaks or 1
contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line i
break as specified in 4.4.5.1.3.c, above.
l 8.
Tuba inspection means an Irispection of the steam generator tube f rom the point of entry (hot leg side) completely around the U - Bend to the top support of the cold leg.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or sleeve all tubes exceeding the plugging Ilmit and plug all defecting sleeves) required by Table 4.4-6.
MILLSTONE - UNIT 2 3/4 4-7a Amendment No. 22,37,52/M,121 l
i Ohi_____________._
SURVEILLANCE REQUIREMENTS (Continued) g 4.4.5.1.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be perfonned at the following frequencies:
The first inservice inspection shall be perfonned after 6 a.
Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be perfonned at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspec-tion results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the, inspection interval may be extended to a maximum of once per 40 months.
b.
If the results of the inservice inspection of a steam generator r conducted in accordance with Table 4.4-6 at 40 month intervals fall into Category C-1, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspec-pr
)
tions satisfy the criteria of Specification 4.4.5.1.3.a; the interval may then be extended to a maximum of once per 40 months.
Additional, unscheduled inservice inspections shall be perfonned c.
on each steam generator in accordance with the first sample inspection specified in Table 4.4-6 during the shutdown subsequent s
{
to any of the following conditions:
1.
Priamry-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2.
l 2.
A seismic occurrence greater than the Operating Basis Earthquake.
3.
A loss-of-coolant accident requiring actuation of the engineered safeguards.
4.
A main steam line or feedwater line break.
MILLSTONE - UNIT 2 3/4 4-7 Amendment No. 22, 37, 83, 101 l
l
(
l REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LEAKAGE l
LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, l
c.
1 GPM total primary-to-secondary leakage through both steam generators and 0.15 GPM through any one steam generator, and d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System.
APPLICABILITY: MODES 1, 2,3 and 4.
ACTION:
a.
With any PRESSURE BOUNDARY LEAKAGE, be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
I b.
With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.4A.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
a.
Monitoring the containment atmosphere particulate radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
Monitoring the containment sump inventory at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c.
Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during steady state operation except when l
operating in the shutdown cooling mode.
l MILLSTONE - UNIT 2 3/44-9 AmendmentNo.%,[,N,N,[1,121
\\..; L _.,'
CHEMISTRY LIMITING CONDITION FOR OPERATION I
3.4.7 The Reactor Coolant System chemistry shall be maintained within i
the limits specified in Table 3.4-1.
APPLICABILITY: ALL MODES.
ACTION:
i MODES 1, 2, 3 and 4 a.
With any one or more chemistry parameter in excess of its Steady State Limit but within its Transient Limit, restore the parameter to within its Steady State Limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
l b.
With any one or more chemistry parameter in excess of its Transient Limit, be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
I liODES 5 and 6
'l With the concentration of either chloride or fluoride in the Reactor Coolant System in excess of its Steady State Limit for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or in excess of its Transient Limit, reduce the pressurizer pressure to 1 500 psia, if applicable, and perform an analysis to l
~~
determine the effects of the out-of-limit condition on the structural 4
integrity of the Reactor Coolant System; determine that the Reactor i
Coolant System remains acceptable for continued operations prior to 4
, increasing the pressurizer pressure above 500 psia or prior to proceeding to MODE 4.
SURVE!LLANCE REQUIREMENTS l
4.4.7 The Reactor Coolant System chemistry shall be determined to be l
l within the limits by analysis of those parameters at the frequencies specified in Table 4.4-1.
l l
l MILLSTONE - UNIT 2 3/4 4-10 b
I l
I
REACTOR COOLANT SYSTEM BASES evidence of mechanical damage or progressive degradation due to ~ design, manuf acturing errors, or inservict; conditions that lead to corrosion. Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant l
chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking.
The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage = 0.15 GPM, l
per steam generator). Cracks having a primary-to-secondary leakage less than l
this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents.
Operating plants have demonstrated that primary-to-secondary leakage of I
0.15 gallon per minute can readily be detected by radiation monitors of steam l
l generator blowdown. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will l
be found during scheduled inservice steam generator tube examinations.
t Plugging or sleeving will be required for all tubes with imperfections exceeding the plugging limit of 40% of the tube nominal wall thickness. Sleeving repair will be limited to those steam generator tubes with a defect between the tube sheet and the first eggerate support.
Tubes containing sleeves with imperfections exceeding the plugging limit will be plugged. Steam generator j
tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be immediately reported to the Comission pursuant to 10 CFR 50.72. Such cases will be considered by the Comission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
MILLSTONE - UNIT 2 B 3/4 4-2a Amendment No. 72,37,57.if.BP.M.
121
~
REACTOR COOLANT SYSTEM BASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAK AGE DETECTION SYSTEMS l
The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary. These deuction systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Sys tem s."
3/4.4.6.2 REACTOR COOLANT SYSTEM LEAKAGE Industry experience has shov/n 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 10 GPM IDENTIFIED LE AKAGE 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 total steam generator tube leakage limit of 1 GPM lor all steam generators ensures that the dosage contribution from the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents.
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 be promptly placed in COLD SHUTDOWN.
The 0.15 GPM Primary to Secondary leakage limitation assures structural Integrity.
A tube with a through-wall circumferential crack which leaks at 0.15 GPM under normal operating conditions retains the structural margins recommended in Regulatory Guide 1.121. In addition, the total leakage under accident conditions would remain below the 1 GPM limit.
MILLSTONE - UNIT 2 B 3/4 4-3 Amendment No. 121
REACTOR COOLANT SYSTEM BASES 3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System contaminants ensure'that corrosion of the Reactor Coolant System is minimized and reduce the poten-tial for Reactor Coolant System leakage or failure due to stress corrosion.
l Maintaining the concentrations of the contaminants within the Steady State l
Limits shown on Table 3.4-1 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 l
fluoride limits are time and temperature dependent.
Corrosion studies show l
that operation may be continued with contaminant concentration levels in
)
excess of the Steady State Limits, up to the Transient Limits, for the l
specified limited time intervals without having a significant effect on the j
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 concentrations to within the Steady State Limits.
k The surveillance requirements provide adequate assurance that concentra-tions 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 sits 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 and a concurrent loss of offsite electrical power.
The ACTION statement permitting POWER OPERATION to continue for limited tinie periods with the primary coolant's specific activity > 1.0 uti/ 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 THERPAL POWER.
MILLSTONE - UNIT 2 B 3/4 4-4 Amendment No.115 FEB s 387 a