ML20092A289

Proposed Tech Specs Incorporating Changes on Spent Fuel Pool Area RMs in Revised Tables 3.3-6 & 4.3-3 & in Bases Section 3/4.3.3.1

ML20092A289
Person / Time
Site:	Millstone
Issue date:	01/31/1992
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20092A281	List: B14019, Application for Amends to License DPR-65,revising TS Tables 3.3-6 & 4.3-3 & Bases Section 3/4.3.3.1, Deleting Inference That Spent RMs Required for Criticality Monitoring.Exemption Incorporated Into License SNM-1335 ML20092A289
References
NUDOCS 9202100039
Download: ML20092A289 (4)

Text

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Qgeket No. 50 336 B14019 Attachment 1 Millstone Nuclear Power Station, Unit No. 2

- Proposed Technical- Specification Change fladiation Monitorina Instrumentation I January 1992 39 9po33, p gj22gggCK05000336 PDR

TABLE 3.3-6

RADIATION MONITORING JNSTRUMENTATION o 3:

3 MINIMUM .

CHANNELS APPLICABLE ALARM / TRIP. MEASUREMENT

] g-It4STRUMENT OPERABLE MODES SETPOINT' RANGE ACTION--

r,

- a

1. AREA MONITORS C

5 a. Spent Fuel Storage -I

[ Ventilation System 2

• 100 mR/hr 10 - 10+4 mR/tir 13 and 15 l Isolation 4

b. Control Room Isolation 1 ALL MODES 2 mR/hr 10-I - 10 mR/hr 16 10 - 108R/hr

' 0

c. Containment High Range 1 1, 2, 3,'& 4 100 R/hr 17 '

5 1

'd. Noble Gas Effluent 1 1, 2, 3, & 4 2 x 10 -I uci/cc 10 10 uci/cc 17 y

Monitor (high range) g (Unit 2 stack)

" 2. PROCESS MONITORS

a. Containment 1 ALL MODES ** the value 10 - 10+6 cpm 14 and (a)

Atmosphere-Particulate determined in accordance with w> specification Dj 4.3.2.1.4. i a

S b. Containment 1 ALL MODES ** the value 10 - 10+6 cpm 14'and (a)

A Atmosphere-Gaseous determined in

== accordance with

? Specification -

4.3.2.1.4.

n E

• With fuel in storage building.

~

• • These radiation monitors are not required to be operable during Type "A" Integrated Leak Rate Testing.

w >

h

TABLE 4.3-3 y

$ RADIATION MONITORING INSTRUhENTATION SURVE'LLANCE RE0dIREMENTS 5 CHANNEL MODES IN WHICH CHANNEL FUNCTIONAL SURVEILLANCE CHANNEL c- CALIBRATION TEST RE0*JIRED z INSTRUMENT CHECK

" 1.' AREA MONITORS

a. Spent Fuel Storage

)

Ventilation System *  !

R N Isolation S R H ALL MODES

b. Control Room Isolation S R** M I, 2, 3, & 4 R c. Containment High Range S R M I, 2, 3, a 4 Y d. Noble Gas Efficant S l

@ Monitor (t ? 31ge)

(Unit 2 E i

2. PROCESS MONITORS l

@ a. Containment Atmosphere- ALL MODES R H R Particulate S 8

5 b. Containment Atmosphere- ALL MODES S R H 2 Gaseous

?

D

\

k*Withfuelinstoragebuilding Hioher ranges-

- ** Calibration of the sensor with a radioactive source need only be performeo on the lowest range.

t may be calibrated' electronically.

u

. l 1hS1B E GA1103 MSLS 31LLL.EiD_ 3BA 2 PR0 LLC 11YL_ED IM1 MIRED _WITY _f1MWLS_RSD lt$1BEf11A110N ((gnLinndl The maximum allowable trip val for these monitors corresponds to calchiated concentratient at ti;e sit. mdary which would not exceed the concentrations listed in 10 CfR part 20 nppendix B. Table 11. Exposura for a year to the concentrations in 10 CIR part 20, Appendix 0. 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 individuul at any point on the exclusion area boundary i for two hours.

Determination of ine '.nonitor'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) tounting efficiency, and 6)3 the background radiation level at the detector. The x/Q of 5.8 x 10 6 sec/m is the highest annual everage x/Q estimated for the site boundary (0.,g9 mileg in ,

the NE sector) for vent releases from the containroent and 7.5 x 10 sec/m 1:

the highest annual average x/Q estimated for an off site location (3 miles in

- the NNE sector) for releases f rom the Unit I stack. This calculation also >

assumes that the isotopic composition is xenon-135 for gaseous radioactivity ,

and cesium 137 for partictglate 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 -MOM 110 RING INS 1RUMENTAT10h

}B4 i RADIATION MAft!TORING LilSTRUMENTAT103 The OPERAB.tLITY 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 setroint 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 c reduce the particslate and iodine radioactivity released to the atmosphere.

Should an accidc<' involving spent fuel occur, the 100 mR/hr actuation setpoint would b; mfficient to limit any consequences at the exclusion area boundary to thos;. ' valuated in the NRC Safety Evaluation, Section 15 (May 1974).

l MILLSTONE - UNIT 2 B 3/4 3-2 0063 I

w:+w c.i t--f-