ML20096H626
| ML20096H626 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (DPR-065) |
| Issue date: | 05/20/1992 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20096H629 | List: |
| References | |
| DPR-65-A-157 NUDOCS 9205270316 | |
| Download: ML20096H626 (6) | |
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NUCLE AR REGULATORY COMMISSION 3
2' W AsHINGTON, D. C. 205$$
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4 NORTHEAST NUCLEAR ENERGY COMPANY
'THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO' FACILITY OPERATING LICENSE Amendment No.157 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 January 31, 1992, 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 L.,
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 Comission;-
C.=
-There is reasonable assurance-(1) that the activities authorized by
'this ' amendment can t-conducted without endangering 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 51 of the Comission's regulations and all applicable requirements have been satisfied.
-9205270316 920520 PDR ADOCK 05000336 P
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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)llows:of Facility Operating License No. DPR-65 is hereby amended to reed as fo (2) Inbnical Specifications The Technical Specificat. ions contained in Appendix A, as revised through Amendment No. 167, and the Ewironmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAD RIM ATORY COMMISSION f^
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- 4. Stol, Director ro ect Directorate I-4 Di sion of Reactor Projects - 1/11 ffice of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
' Specifications
. Date of. Issuance: May 20, 1992 l
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81TACHMENT 10 llCENSE /Nih3HENT NO.157 FACillTY OPERATING tlCF.NSE NO. DPR-65 QQCKET NO. 50-336 i
Replace the following pages of the Appendix e rechnical Specn'ications with the enclosed pages. The revised pages a,e identified by amendment number and contain vert. cal lines indicating the areas of change.
Remove Insert 3/4 3-27 3/4 3-27 3/4 3-29 3/4 3-29 8 3/4 3-2 B 3/4 3-2 l
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.lRBLE 3.3-6 RADI ATION MONITORING INSTRlHENTATION
. o 3:
F MINIMUM'
~h CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT g INSTRUMENT OPERABLE-MODES SETPOINT RANGE ACTION
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- 1. AREA MONITORS C5 a.
Spent. Fuel Storage
[
Ventilation System 2
100 mR/hr 10
- 10*4 mR/hr 13 and 15 l
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- Isolation.
~I b.
Control Room Isolation 1
ALL MODES 2 mR/hr 10
- lu mR/hr 16 0
8
.. Containment High Range i
1, 2, 3, & 4 100 R/hr 10 - 10 R/hr 17
.d.
Noble Gas Effluent 1
1, 2, 3,-& 4 2 x 10'I uci/cc 10
- 10 uci/,c 17
~3 5
Monitor (high range)
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(Unit 2 stack)
- 2. PROCESS MONITORS a.
Ct,atainment I
ALL MODES **
the value 10 - 10+6 cpm 14 and (a)
Atmosphere-Particulate determined in accordan?.e with gg specification og 4.3.7.1.4.
a G2 b.
Containtnent 1
ALL MODES **
the value 10 - 10+6 cm 14 and (a)
"A Atmosphere-Gaseous determined in g
accordance with Specification 4.3.2.1.4.
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- With fuel in storage building.
- These radiation monitors are not required to be operable during Type "A" Integratei leak Rate Testing.
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RADIATION HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
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CHANNEL MODES IN WlilCil
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CHANNEL CHANNEL
. FUNCTIONAL SURVEItLANCE 2
NSTRUMENT CHECK CALIBRATION TEST REQUIRED
" 1. AREA MONITORS-a.
Spent fuel Storage Ventilation System l
Isolation S
R H
b.
Control Room Isolation S
R H
ALL MODES l
R c.
Containment liigh Range S
R**
M 1, 2, 3, & 4 i
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d.
Noble Gas Effluent.
S R
H 1, 2, 3, & 4 l-Honitor (high range)
(Unit 2 Stack)
- 2. PROCESS MONITORS a.
Containment Atmosphere-R Particulate S
R fi ALL N00.~S 2
5, b.
Containment Atmosphere-Gaseous ~
S R
H All MODES
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. @ *With fuel in storage building.
- ralibration of the sensor witn a radioactive soitrce need only be performed on the lowest range. Higher ranges i
u ma; be calibrated electronically.
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y INSTRUMENTATION BASES 3/4.3.1 AND 3/4.3.2 PROTECTIVE AND U1 GLEE.R.LD SAf*TY FEATURES (ESf)
INSTRUMENTAT10N (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 11.
Exposure for a year to the concentrations in 10 CFR Part 20, Appendix B.
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/0), 2) isotopic composition of the sample, 3) sample-flow rate, 4) sample collection efficiency, 5) counting efficiency, and 6)3 the background radiation level at th$ 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.
the NE sector) for vent releases from the containment and 7.5 x 10,p mileg in sec/m is the highest annual average x/Q estimated for an off-site iocation (3 miles in the NN: sector) for releases from the Unit I stack.
This calculation also assumes that the isotopic composition is xenon-133 for gaseous radioactivity and cesium 137 for particglate radioactivity (Half Lives greater than 8 days).
The upper. limit of 5 x 10 cpm is approximately 90 percent of full instrument scale.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring cFannels 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 raaiation level trip setpoint is exceeded.
The spent fuel storage area 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 I
reduce the particulate and iodine radioactivity released to the atmosphere.
Should 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).
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t MILLSTONE - UNIT 2 B 3/4 3-2 Amendment No. 157 0053 lL