ML20128A914
| ML20128A914 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/19/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128A920 | List: |
| References | |
| RTR-REGGD-01.095, RTR-REGGD-1.095 NUDOCS 8507030066 | |
| Download: ML20128A914 (13) | |
Text
f EEroq'o UNITED STATES c
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NUCLEAR REGULATORY COMMISSION c.
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- E WASHINGTON, D. C. 20555
\\...../
NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT N0. 2 MENDMENT TO FACILITY OPERATING LICENSE Amendment No.100 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 April 2, 1985, 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 confonnity 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 safeiy 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 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 51 of the Comission's regulations and all applicable requirements have been satisfied.
8507030066 850619 PDR ADOCK 05000336 P
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. 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.100, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$b Edward J.
utcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 19, 1985
ATTACHMENT TO LICENSE AMENDMENT N0.100 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are provided to maintain document completeness.
Remove Pages Insert Pages 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29 3/4 3-42 3/4 3-42 3/4 7-17 '
3/4 7-17 3/4 7-18 3/4 7-18 B 3/4 3-4 B 3/4 3-4
TABLE 3.3-6 F
~
0; RADIATION MONITORING INSTRUMENTATION 8m MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION c-5 1.
AREA MONITORS ro a.
Spent Fuel Storage Criticality Monitor 2
< 100 mR/hr 10'I - 10*4 mR/hr 13 and 15 and Ventilation System Isolation 4
b.
Control Room Isolation 1
ALL MODES
< 2 mR/hr 10-I - 10 mR/hr 16 2.
PROCESS M0hlTORS w
b a.
Containment 1
ALL MODES
< the value 10 - 10+6 cpm 14 and (a)
Atmosphere-Particulate determined in accordance with Specification 4.3.2.1.4.
b.
Containment 1
ALL MODES
< the value 10 - 10+6 cpm 14 and (a) k Atmosphere-Gaseous ifetemined in E
accordance with Specification 5
4.3.2.1.4.
F 3
- With fuel in storage building.
TABLE 3.3-6 (Continued)
TABLE NOTATION (a)
During MODE 6, also comply with the ACTION requirements of Specification 3.9.9, as applicable.
ACTION 13 -
With the number of area moniters OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 14 -
With the number of process monitors OPERABLE less than required b either (a)y the Minimum Channels OPERABLE requirement obtain and analyze grab samples of the moni-tored parameter at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (b) use a Constant Air Monitor to monitor the parameter.
ACTION 15 -
With the number of area monitors OPERABLE less than required by the Minimu.n Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.13.
ACTION 16 -
With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
5 MILLSTONE - UNIT 2 3/4 3-28 Amendment No. RE,100
TABLE 4.3-3 I
{
RADIATION MONITORING INSTRUENTATION SURVEILLANCE REQUIREMENTS z
CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE
[
INSTRlMENT CHECK CALIBRATION TEST REQUIRED
=
i M
1.
AREA MONITORS N
a.
Spent Fuel Storage Criticality Monitor and Ventilation l
System Isolation S
R M
j b.
Control Room m
g Isolation S
R M
ALL MODES
[
2.
PROCESS MONITORS e
i a.
Containment Atmosphere-l Particulate S
R M
ALL MODES i
l b.
Containment Atmosphere-
)
Gaseous S
R M
ALL MODES l
k a
- s I
k i
a J
3 1
8
- With fuel in storage b-
- ding I
l 1
i
INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with at least one OPERABLE detector segment in each core quadrant on each of the four axial elevations containing incore detectors and as further specified below:
a.
For monitoring the AZIMUTHAL POWER TILT:
At least two quadrant symetric incore detector segment groups at each of the four axial elevations containing incore detectors in the outer 184 fuel assemblies with sufficient OPERABLE detector segments in these detector groups to compute at least two AZIMUTHAL POWER TILT values at each of the four axial elevations containing incore detectors, b.
For recalibration of the excore neutron flux detection system:
1.
At least 75% of all incore detector segments, 2.
A minimum of 9 OPERABLE incore detector segments at each detector segment level, and 3.
A minimum of 2 OPERABLE detector segments in the inner 109 fuel assemblies and 2 OPERABLE segments in the outer 108 fuel assemblies at each segment level.
c.
For monitoring the UNRODDED PLANAR RADIAL PEAKING FACTOR, the UNRODDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate:
1.
At least 75% of all incore detector locations, 2.
A minimum of 9 OPERABLE incore detector segments at each detector segment level, and 3.
A minimum of 2 OPERABLE detector segments in the inner 109 fuel assemblies and 2 OPERABLE segments in the outer 108 fuel assemblies at each segment level.
An OPERABLE incore detector segment shall consist of an OPERABLE rhodium detector constituting one of the segments in a fixed detector string.
An OPERABLE incore detection location shall consist of a string in which at least three of the four incore detector segments are OPERABLE.
MILLSTONE - UNIT 2 3/4 3-30 Amendment No. 25, 45 m
l5 TABLE 4.3-6 r-REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION c=
=
El 1.
Wide Range Logarithmic M
N.A.
n>
Neutron Flux 2.
Reactor Trip Breaker Indication M
N.A.
3.
Reactor Cold Leg Temperature M
R 4.
Pressurizer Pressure a.
Low Range M
R R
b.
High Range M
R w
5.
Pressurizer Level M
R 6.
Steam Generator Level M
R 7.
Steam Generator Pressure M
R
.3
INSTRUMENTATION CHLORINE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.3.3.6 Two separate and independent chlorine detection systems, with their alarm / trip setpoints adjusted to actuate at a chlorine concentra-tion of 11 ppm, shall be OPERABLE with a detector located in each l
control room outside air intake duct.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a.
With one chlorine detection system inoperable, restore the inoperable detection system to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recircu-lation mode of operation.
b.
With no chlorine detection system OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.6 Each chlorine detection system shall be verified energized at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and demonstrated OPERABLE by performance of a CHANNEL CALIBRATION at least once per 18 months.
MILLSTONE - UNIT 2 3/4 3-42 Amendment No. (5,100
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.
Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses t's test procedures of Regulatory Positions C.S.a. C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flo'w rate is 2500 cfm i 10%.
I 2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978. The carbon sample shall have a removal efficiency of > 95 percent.
3.
Verifying a system flow rate of 2500 cfm + 10% during system i
operation when tested in accordance with KNSI N510-1975.
d.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
e.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 2500 cfm i 10%.
I 2.
Verifying that on a recirculation signal, the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks.
f.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2500 l
cfm i 10%.
MILLSTONE - UNIT 2 3/4 7-17 Amendment No. 25, 72, 100
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 9 After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2500 cfm + 10%.
g 5
MILLSTONE - UNIT 2 3/4 7-18 Amendment No. 72,100
v 1NSTRUMENTATION BASES 3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that suffi-cient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility.
3/4.3.3.4. METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs."
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
MILLSTONE - UNIT 2 B 3/4 3-3 Amendment No. 25,49
F 4
INSTRUMENTATION BASES 3/4.3.3.6 CHLORINE DETECTION SYSTEMS The operability of the chlorine detection systems ensures that an accidental chlorine release will be detected promptly and the necessary protective actions will be automatically initiated to provide protection for control room personnel.
Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically isolate the control room and initiate its operation in the recirculation mode of operation to provide the required protection.
The chlorine detection systems required by this specification are consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release".
l 3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages.
Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumenta-tion is restored to OPERABILITY.
3/4.3.3.8 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident.
This capability is consistent with the recommendations of NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations".
MILLSTONE - UNIT 2 B 3/4 3-4 Amendmentlio.35,Af,/gg,100