ML20084S100
| ML20084S100 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/16/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20084S102 | List: |
| References | |
| TAC-49061, NUDOCS 8405230611 | |
| Download: ML20084S100 (11) | |
Text
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UNITED STATES E y,,( *' k NUCLEAR REGULATORY COMMISSION l
- i '
y WASHINGTON, D. C. 20555
.1
's NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE HESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT T0 FACILITY OPERATING LICENSE Amendment No. 95 License No. DPR-65 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated October 22, 1982 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; 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 arcendment can be conducted without eridangering 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 amendment will not be inimical to the comon 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 SI of the Comission's regulations and all applicable requirements have been satisfied.
8405230611 840516 PDR ADOCK 05000336 P
. 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-65 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, are hereby incorporated in the license.
The licen'see shall operate the facility in accordance with the Technical Specifica-tions.
3.
This license amendment is effective on the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical I
Specifications Date of Issuance:
May 16, 1984
ATTACHMENT TO LICENSE AMENDMENT NO. 95 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET N0. 50-336 Remove and replace the following pages of the Appendix A Technical Specifica-tions with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corre-sponding overleaf pages are provided to maintain document completeness.
Remove Insert 3/4 1-25 3/4 1 3/4 5-1 3/4 5-1 3/4 6-1 3/4 6-1 3/4 6-6 3/4 6-6 1
4 4
REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS (Continued) e 2
~
LIMITING CONDITION FOR OPERATION b) The CEA group (s) with the inoperable position indicator i-is fully inserted, and subsequently maintained fully inserted, while maintaining the withdrawal sequence and THERMAL POWER level required by Specification 3.1.3.6 and when this CEA group reaches its fully inserted position, the " Full In" limit of the CEA with the inoperable position indicator is actuated and verifies this CEA to be fully inserted.
Subsequent operation l
shall be within the limits of Specification 3.1.3.6.
t 4.
If the failure of the' position indicator channel (s) is during STARTUP, the CEA group (s) with the inoperable position indicator channel must be moved to the " Full Out" l
position and verified to be fully withdrawn via a "Ful_1 Out" indicator within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The provisions of Specifica-tion 3.0.4 are not applicable.
2 c.
With a maximum of one reed switch position indicator channel per group or one pulse counting position indicator channel per group 4
i inoperable and the CEA(s) with the inoperable position indicator i-channel at either its fully' inserted position or fully withdrawn position, operation may continue provided:
i 1.
The position of this CEA is verified insnediately and at l
1 east once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter by its " Full In" or
" Full out" limit (as applicable),
2.
The fully inserted CEA group (s) containing the inopera_ble i-position indicator channel is subsequently maintained fully l
inserted and s
3.
Subsequent operation is within the limits of Specification -
l 3.1.3.6.
d.
With one or more pulse counting position indicator channels in-l operable, operation in MODES 1 and 2 may continue for up to 24 l
hours-provided all of the reed switch position indicator channels are OPERABLE.
i SURVEILLANCE REQUIREMENTS I-4.1 '. 3. 3 Each position',ndicator channel shall be determined to be OPERABLE by verifying the pulse counting position indicator channels and the reed i
switch position indicator channels agree within 6 steps at least once per 12 Murs except during time intervals when the Deviation circuit is in-i L
operable, then compare the pulse l counting position indicator and reed switch j
position indicator-channels at least once.per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
l l
L MILLSTONEL UNIT 2 3/4 1-25 Amendment;No.
95 L
L a.
z.,
.. a.
REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION i
3.1.3.4 The individual full length -(shutdown and control) CEA drop j
time, from a fully withdrawn position,-shall be < 2.75 seconds from I
when electrical power is interrupted,to the CEA cTrive mechanism until the CEA reaches its 90 percent insertion position with:
i-T,yg >_515 F, and l
a.
b.
All reactor coolant pumps operating.
APPLICABILITY: MODE 3.
ACTION:
a.
With the drop time of any full length CEA determined to exceed l
the above limit, restore the.CEA drop time to wi-thin the above limit prior to.proceeaing to MODE 1 or 2.
i b.
With the CEA drop times within limits but determined at.less i
than full reactor coolant flow, operation may -proceed provided THERMAL POWER is restricted to less than or equal to the maximum THERMAL POWER level allowable for the reactor coolant pump cambination operating at the time of CEA drop time determination.
i SURVEILLANCE REQUIREMENTS i
4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality:
a.
For a.ll CEAs following each removal of the reactor vessel l
- head, b.
For specifical'ly affected individual CEAs following any main-tenance on or modification to the CEA drive system which could
- affect 'the drop time of.those specific CEA, and 4
c.
At least once per 18 months..
MILLSTONE UNIT 2 3/4-1 AmendmentNo.38,jg,90 t
r m
-. -4
+n
3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:
a.
The isolation valve open and the power to the valve operator
- removed, b.
Between 1080 and 1190 cubic feet of borated water, l
~
c.
A minimum boron concentration of 1720 PPM, and d.
A nitrogen cover-pressure of between 200 and 250 psig.
APPLICABILITY: MODES 1, 2 and 3.*
ACTION:
4 a.
With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in HOT SHUTDOWN within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
1.
Verifying the water level and nitrogen cover-pressure in the tanks, and 2.
Verifying that each safety injection tank isolation valve i
l is open.
l
- With pressurizer pressure > 1750 psia.
MILLSTONE - UNIT 2 3/4 5-1 Amendment No. 95
l i
EMERGENCY CORE COOLING SYSTEMS SAFETY INJECTION TANKS (Continued)
SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 31 days and at each solution volume increase of > 1% of tank volume by verifying the boron. concentration of the safety injection tank solution.
c.
At least once per 31 days by. verifying that the closing coil in the valve breaker cubicle is removed.
d.
Verifying at least once per 18 months that_the safety injection tank isolation valves open automatically before the. Reactor Coolant System pressure exceeds 1750 psia and on a safety in-jection signal.
e 1
i i
i t
MILLSTONE - UNIT 2 3/4 5-2' Amendment No. 45
F L
t 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 -PRIMARY CONTAINMENT j
CONTAINMENT INTEGRITY l
i LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
f APPLICABILITY: MODES 1, 2, 3 and 4.
ACTIO_N:
i Without primary CONTAINMENT INTEGRITYT, restore CONTAINMENT INTEGRITY within i
one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the fo110 wing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i SURVEILLANCE REQUIREMENTS i
4.6.1.1 Primary CONTAINMENT INTEGRITY shall-be demonstrated:
a.
At least once per 31 days by verifying that all penetrations not capable of being closed by OPERABLE containment automatic isola-tion valves and-required to be closed during accident conditions are closed by valves, blind flanges nr deactivated automatic
. valves secured in their positions, except as provided in Table j
3.6-2 of Specification 3.6.3.1.
4 l
b.
At least once per 31 days by verifying the equipment hatch is I
closed and sealed.
c.
By verifying the containment air lock is OPERADLE per. Specifica-
.[
tion 3.6.1.3.
d.
After each closing of a penetration subject to type B testing (except the contaiiment air lock), if opened following a Type i
A or B test, by leak rate testing the seal with gas at.Pa (54 l
psig) and verifying that when the. measured leakage rate for -
1 these seals is added to the leakage rate determined pursuant to Specification 4.6.~1.2.d for all other Type B and C penetra-l tions, the combined leakage rate is less than or_ equal to 0.60 La-
- 0peration within the time allowances of the ACTION statements of Specifica-
_ tion 3.6.1.3 does not constitute a loss of CONTAINMENT INTEGRITY, MILLSTONE - UNIT 2~
3/4 6-l' Amendment No. 25, 95 l
t.
CONTAINMENT SYSTEMS l
CONTAINMENT LEAKAGE i
LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of 1 L 0.50 percent by weignt of the containment. air per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> $,at P, 54 psig.
a b.
A combined leakage rate of < O.60 L for all penetrations and valvessubjecttoTypeBan?CtestswhenpressurizedtoP.
3 c.
A combined leakage rate of 1 0.017 L for all penetrations identifiedinTable3.6-1asseconda@ycontainmentbypass leakage paths when pressurized to P
- a
}
APPLICABILITY: MODES 1, 2, 3 and 4.
i ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L,
r (b) with the measured combined leakage rate for all a
penetrations and valves subject to Types B and C tests exceeding 0.60 L or (c) with the combined bypass leakage rate exceeding 0.017 L, restor 8, a
the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and pro-i visons of ANSI N45.4-1972:
a.
Three Type A tests (0verall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during The third tesl o(54 psig) during-each 10-year service period.
shutdown.at P f each set shall be conducted during the shutdown for the 10-year plant inservice insoection.
I.
MILLSTONE - UNIT 2 3/4 6-2
' i'i U
TABLE 3.6-1 ElM
. SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS PENETRATION N0.
SYSTEM RELEASE LOCATION
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N 14 Normal Sump Unit 2 Stack via Aerated Waste Drain Tank Vent.
67 Refueling Water Purification Unit 2 Stack via Auxiliary Building Ventilation. System above Spent Fuel Pool.
68 Refueling Water Purification Unit 2 Stack via Auxiliary Building Ventilation System above Spent Fuel R
Pool.
s T
m
1 CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 The containment air lock shall be OPERABLE with:
a.
Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of.< 0.06 L at Pa (54 psig).
a APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
a.
With one containment air lock door inoperable:
1.
Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.
3 2.
Operation may then continue until performance of the next required overall air lock-leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.
3.
Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1 4.
The provisions of Specification 3.0.4 are not applicable if the outer air lock door is inoperable.
b.
With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status 4
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hgurs and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
a.
After each opening, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying no detectable seal leakage by pressure decay when the volume between the door seals is pressurized to greater than or equal 4
to 25 psig for at least 15 minutes, MILLSTONE - UNIT 2 3/4 6-6 Amendment No. 95
.. - _ _..