ML19283B812
| ML19283B812 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/01/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19283B813 | List: |
| References | |
| NUDOCS 7903260393 | |
| Download: ML19283B812 (17) | |
Text
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UNITED STATES
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[t NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 s.,4 r gw ag THE CONNECTICUT LIGHT AND POWER COMPA!!Y, THE HARTFORD ELECTRIC LIGnT COMPANY, WESTERN MAS $ACnU$ETTS ELECTRIC COMPANY, AND NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDP.ENT TO FACILITY OPERATING LICENSE Amendment No. 49 License Nc. OPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by The Connecticut Light and Power Company, The Hartford Electric Light Company, Western Massachusetts Electric Company and Northeast Nuclear Energy Company (the licensees) dated August 15, 1978, complies with the standards and recuirements 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 coerate 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 amencment can be conducted without endangering the healtn 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 security or to the health and safety of the puclic; and E.
The issuance of this amendment is in accordance witn 10 CFR Part 51 of tne Ccnmission's regulations and all acclicable recuirements have been sacisfied.
. 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 Soecifications The Technical Specifications contained in Appendices A and 3, as revised through Amendment No. 49, are hereby incorporated in the 'icense.
The licensees shall operate the facility in accordance with the Technical Soecifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0f1 MISSION
<O Robert W. Reid, Chief Operating Reactors Branch #4 Disision of Operati'ig Reactors Attacnment:
Changes to the Technical Specifications Date of Issuance:
March 1,1979
ATTACHMENT TO LICENSE AMENDMENT NO. 49 FACILITY OPERATING LICENSE NO. OPR-65 00CKET fi0. 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 also provided to maintain document completeness.
Pages IX 3/4 3-11 3/4 3-19 3/4 3-27 3/4 3-29 8 3/4 3-1 B 3/4 3-2 B 3/4 3-3 B 3/4 3-4 (added)
INDEX BASES PAGE SECTION B 3/4 0-1 3/4.0 APPLICABILITY..........................................
3/4.1 REACTIVITY CONTROL SYSTEMS B 3/4 1-1 3/4.1.1 BORATION CONTR0L.....................................
B 3/4 1-2 3/4.1.2 B0 RATION SYSTEMS.....................................
B 3/4 1-3 3/ 4.1. 3 MOVABLE CONTROL ASSEMBLIES...........................
3/4.2 POWER DISTRIBUTION LIMITS B 3/4 2-1 3/4.2.1 LINEAR HEAT RATE.....................................
T 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - F B 3/4 2-1 xy TOTALINTEGRATEDRADIALPEAKINGFACTOR-Ff...........B3/42 3/4.2.3 B 3/4 2-1 3/4.2.4 AZIMUTHAL POWER TILT.................................
B 3/4 2-2 3/4.2.5 FUEL RESIDENCE TIME..................................
B 3/4 2-2 3/4.2.6 DNB MARGIN...........................................
3/4.3 INSTRUMENTATION B 3/4 3-1 3/4.3.1 PROTECTIVE INSTRUMENTATION...........................
3/4.3.2 ENGINEERED SAFETY FEATURE INSTRUMENTATION............B 3/4 3-1 B 3/4 3-2 3/4.3.3 MONITORING INSTRUMENTATION.....................
Amendment No. 32,40 MILLSTONE - UNIT 2 IX
INDEX BASES PAGE SECTION 3/4.4 REACTOR COOLANT SYSTEM B 3/4 4-1 3/4.4.1 REACTOR COOLANT L00PS................................
B 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY VALVES............................
i B 3/4 A-2 3/4.4.4 PRESSURIZER..........................................
B 3/4 4-2 3/4.4.5 STEAM GENERATORS.....................................
B 3/4 4-3 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE.......................
B 3/4 4-4 3/4.4.7 CHEMISTRY............................................
B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY...................
B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS..........................
B 3/4 4-11 3/4.4.10 STRUCTURAL INTEGRITY.................................
B 3/4 4-12 3/4.4.11 CORE BARREL M0VEMENT.................................
3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
B 3/4 5-1 3/4.5.1 SAFETY INJECTION TANKS...............................
3/4.5-2 and 3/4.5-3 ECCS SUBSYSTEMS..........................
B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK (RWST)..................
B 3/4 5-2 MILLSTONE - UNIT 2 X
INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) 4.3.2.1.3 The ENGINEERED SAFETY FEATURE 5 RESPONSE TIME of each ESF function shall be demonstrated to be within the limit at least once per Each test shall include at least one channel per function 18 months.
such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ESF function as shown in the " Total No. of Channels" Column of Table 3.3-3, The trip value shall be such that the containment purge 4.3.2.1.4 effluent shall not result in calculated concentrations of radioactivity offsite in excess of 10 CFR Part 20, Appendix B, Table II.6 Fortge purposes of calculating this trip value, a x/Q = 5.8 x 10- sec/m shall be used when the system is aligned to purge through the building vent shall be used when the system is aligned to 3
and a x/Q = 7.5 x 10 s sec/m purge through the Unit i stack; the gaseous and particulate (Half Lives greater than 8 days) radioactivity shall be assumed to be xenon.133 and cesium-137, respectively. However, the setpoints shall be no greater than 5 x 105 cpm.
MILLSTONE - UNIT 2 3/4 3-11 Amendment No 09'
TABLE 3.3-3 h
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Gd MINIMUM M
TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1.
SAFETY INJECTION (SIAS) a.
Manual (Trip Buttons) 2 1
2 1,2,3,4 6
b.
Containment Pressure -
High 4
2 3
1,2,3 7
c.
Pressurizer Pressure -
Low 4
2 3
1,2(e),3(a) 7 2.
CONTAINMENT SPRAY (CSAS) a.
Manual (Trip Buttons) 2 1
2 1,2,3,4 6
R b.
Containment Pressure --
{
High - High 4
2(b) 3 1,2,3 7
3.
CONTAINMENT ISOLATION (CIAS) a.
Manual CIAS (Trip Buttons) 2 1
2 1,2,3,4 6
b.
Manual SIAS (Trip Buttons) 2 1
2 1,2,3,4 6
c.
Containment Pressure -
High 4
2 3
1,2,3 7
d.
Pressurizer Pressure -
Low 4
2 3
1,2(e),3(a) 7
i5 U
TABLE 3.3-4 (Continued)
EtlGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES ALLOWABLE
-i FUNCTIONAL UNIT TRIP VALUE VALUES m
S.
ENCLOSURE BUILDING FILTRATION (EBFAS) a.
11anual EBFAS (Trip Buttons)
Not Applicable Not Applicable b.
Not Applicable Not Applicable c.
Containment Pressure - liigh 1 5 psig 1 5 psig d.
Pressurizer Pressure - Low
> 1600 psia
> 1600 psia 6.
C0flTAINMENT SUMP RECIRCULATION (SRAS)
R a.
Manual SRAS (Trip Buttons)
Not Applicable Not Applicable
- ^
Y b.
Refueling Water Storage Tank - Low 48 + 18 inches above 48 + 18 inches above G
tanlibottom tanIIbottom 7.
CONTAINMENT PURGE VALVES ISOLATION a.
flanual CIAS (Trip Buttons)
Not Applicable Not Applicable b.
fianual SIAS (Trip Buttons)
Not Applicable Not Applicable c.
Automatic CIAS Actuation Logic Not Applicable Not Applicable d.
Containment Radiation - liigh Gaseous Activity
< the value determined
< the value determined p
Tn accordance with In accordance with m
h Specification 4.3.2.1.4 Specification 4.3.2.1.4.
to 5
Particulate Activity (llalf Lives
< the value determined
< the value determined
~g greater than 8 days)
Tn accordance with In accordance with Specification 4.3.2.1.4.
Specification 4.3.2.1.4.
3
TABLE 3.3-4 (Continued) f5 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES G
-4 EE ALLOWABLE
[
FUNCTIONAL UNIT TRIP VALUE VALUES E!
8.
LOSS OF POWER a
n>
a.
4.16 kv Emergency Bus Undervoltage (Undervoltage relays) - level one t 2912 volts 1 2912 volts b.
4.16 kv Emergency Bus Undervoltage 1 3700 volts with 3 3700 volts with (Undervoltage relays) - level two an 8.0 + 2.0 second an 8.0 + 2.0 second time deTay time deTay M
u Y
8 2T a
R ae O.
3 l-Te@
TABLE 3.3-6 m
RADI ATI0ff MONITORING IftSTRUMErlTATI0ft E
G MINIMUM CilANf4ELS APPLICABLE ALARM / TRIP MEASUREf1ErlT n3 INSTRUMENT OPERABLE MODES SETP0IllT RAflGE ACTI0ft 1.
AREA MONITORS a.
Spent Fuel Storage
-j
- 4 1 100 mR/hr 10
- 10 mR/hr 13 and 1S Criticality Monitar 2
and Ventilation System Isolation 2.
PROCESS MONITORS a.
Containment 1
ALL MODES
< the value 10 - 10+6 cm 14 and (a)
Atmosphere-Particulate determined in accordance with specification 4.3.2.1.4.
b.
Containment 1
ALL MODES 1 the value 10 - 10+6 cpm 14 and 'a)
Atmosphere-Gaseous determined in accordance with Specification l
- 4. 3. 2.1,4.
E i
m h
an With fuel in storage building.
- ~
so
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 monitors 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 by the Minimum Channels OPERABLE requirement either (a) 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 Minimum Channels OPC'ABLE requirement, comply with the ACTION requirements of Specification 3.9.13.
I MILLSTONE - UNIT 2 3/4 3-28 Amendment No. 25
15 F$
TABLE 4.3-3 9
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS m
E CHANNEL MODES IN W111CH q
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED m
1.
AREA MONITORS a.
Spent Fuel Storage Criticality Monitor and Ventilation System Isolation S
R M
2.
PROCESS MONITORS
[
a.
Containment Atmosphere-Particulate S
R H
ALL MODES b.
Containment Atmosphere-Gaseous S
R H
ALL MODES With fuel in storage building 9
8,,
INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with at least one OPERABLE detector segmert in each core quadrant on each of the four axial elevations contain.ng incore detectors and as further specified below; For monitoring the AZIMUTHAL POWER TILT:
a.
At least two quadrant symetric incore detector segment groups at each of the four axial elevations containing incere 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.
For monitoring the UNRODDED PLANAR RADIAL PEAKING FACTOR, c.
the UNRODDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate:
1.
At least U% of all incore detector locations, 2.
A minirr._m 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.
l MILLSTONE - UNIT 2 3/4 3-30 Amendment "'
25, 45
3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and bypasses ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combi-nation thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to per,it a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient con-The integrated operation of each of these systems is consistent ditions.
with the assumptions used in the accident analyses.
The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable The periodic surveillance tests per-to the original design standards.
formed at the minimum frequencies are sufficient to demonstrate this capability.
The measurement of response time at the specified frequencies pro-vides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the No credit was taken in the analyses for those channels accident analyses.
with response times indicated as not applicable.
Response time may be demonstrated by any series of sequential, over-lapping or total channel test measurements provided that such tests Sensor response demonstrate the total channel response time as defined.
time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.
The containment airborne radioactivity monitors (gaseous and particulate) are provided to initiate closure of the containment purge valves upon detection of high radioactivity levels in the containment.
Closure of these valves prevents excessive amounts of radioactivity from being released to the environs in the event of an accident.
MILLSTONE - UNIT 2 8 3/4 3-1 Amendment No.49
INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)
INSTRUMENTATION (Continued)
The maximum allowable trip value for these monitors corresponds to calculated concentrations at the site boundary which would not exceed the concentrations listed in 10 CFR Part 20, Appendix B, Table II.
Exposure for a year to the concentrations in 10 CFR Part 20, Appendix 8.
Table corresponds to a total body dose to an individual of 500 mrem which is well below the guidelines of 10 CFR Part 100 for an individual at any point on the exclusion area boundary for two hours.
Determination of the monitor's trip value in counts per minute, which is the actual instrument response, involves several factors including: 1) the atmospheric dispersion (x/Q), 2) isotopic composition of the sample, 3) sample flow rate, 4) sample collection efficiency, 5) countingefficiency,and6)thebackgrgundradiationlevelatthe detector.
The x/Q of 5.8 x 10-6 sec/m is the highest annual average x/Q estimated for the site boundary (0.48 miles in the NE sector) for vent releases from the containment and 7.5 x 10 8 sec/m3 is the highest annual average x/Q estimated for an off-site location (3 miles in the NNE sector) for releases from the Unit I stack.
This calculation also assumes that the isotopic composition is xenon-133 for gaseous radio-activity and cesium-137 for particulate radioactivity (Half Lives greater 5 cpm is approximately 90 percent than 8 days). The upper limit of 5 x 10 of full instrument scale.
3/4.3.3 MO MTORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that
- 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
The spent fuel storage area monitors are provided to serve two functions.
First, the monitors are required by 10 CFR Part 70 to detect accidental criticality and to provide an alarm warning to personnel.
A setpoint of 100 mR/hr meets the sensitivity requirements of 10 CFR Part 70 Second, the monitors provide a signal to direct the ventilation exhaust from the spent fuel storage area through a filter train when the dose rate exceeds the setpoint.
The filter train is provided to reduce the Should particulate and iodine radioactivity released to the atmosphere.
an accident involving spent fuel occur, the 100 mR/hr actuation setpoint would be sufficient to limit any consequences at the exclusion area boundary to those evaluated in the NRC Safety Evaluation, Section 15 (May 1974).
MILLSTONE - UNIT 2 B 3/4 3-2 Amendment No. 23, M
INSTRUMEiiTATION 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 irtportant 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 recomendations of Regulatory Guide 1.23 "0nsite Meteorological Programs."
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to pemit 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
INSTRUMENTATION BASES i
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 specificatico are consistent with the recommendations of Regulatory Guide 1.95, "Protec6'on of Nuclear Power Plant Control Room Operators Against an Accidental Chivi :ne Release."
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 poten-tial 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 instrumentation is restored to OPERABILITY.
MILLSTONE - UNIT 2 B 3/4 3-4 Amendment No. 35,109