JPN-93-090, Proposed Tech Specs Eliminating Inconsistency Between RCS Leakage Detection & Operability Requirements in LCOs 3.6.D.1 & 3.6.D.4

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Proposed Tech Specs Eliminating Inconsistency Between RCS Leakage Detection & Operability Requirements in LCOs 3.6.D.1 & 3.6.D.4
ML20059B422
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 12/29/1993
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20059B398 List:
References
JPN-93-090, JPN-93-90, JPTS-92-031, JPTS-92-31, NUDOCS 9401040128
Download: ML20059B422 (19)
v • d • e


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Attachment I to JPN-93-090 PROPOSED TECHNICAL SPECIFICATION CHANGES RCS LEAK DETECTION LCO i

(JPTS-92-031)

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New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 9401040128 931229

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DPR-59 PDR ADOCK 05000333 PDR e

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Attachment I to JPN-93-090 PROPOSED TECHNICAL SPECIFICATION CHANGES RCS LEAK DETECTION LCO (JPTS-92-031) t i

i I

a New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 l

DPR-59

JAFNPP LIST OF TABLES (Cont'd) l Table Iltla Paae-l 4.2-8 Minimum Test and Calibration Frequency for Accident Monitoring 86 Instrumentation I

4.6-1 Snubber Visual inspection interval 161 4.6-2 Minimum Test and Calibration Frequency for Continuous Atmosphere 162a Monitoring System 4.7-1 (DELETED) 210 4.7-2 Exception to Type C Tests 211 3.12-1 Water Spray / Sprinkler Protected Areas 244j 1

3.12-2 Carbon Dioxide Protected Areas 244k 3.12-3 Manual Fire Hose Stations 2441 4.12-1 Water Spray / Sprinkler System Tests 244q 4.12-2 Carbon Dioxide System Tests 244r 4.12 3 Manual Fire Hose Station Tests 244s 6.2-1 Minimum Shift Manning Requirements 260a 6.10-1 Component Cyclic or Transient Limits 261 Amendment No. - 20, 22,-G2, l ' 1,130,13',150,173,180,181, vi 1

JAFNPP 3.6 (cont'd) 4.6 (cont'd) 4.

Except as specified in 3.6.C.3 above, th6 reactor coolant

. water shall not exceed the following limits with steaming rates greater than or equal to 100,000 lb/hr and during reactor shutdowns.

Conductivity 5 pmho/cm Chloride ion 0.5 ppm 5.

If Specification 3.6.C cannot be met, the reactor shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D.

Coolant Leakace D.

Coolant Leakace l

1.

Anytime irradiated fuel is in the reactor vessel and the 1.

Reactor coolant leakage rate inside the primary l

reactor coolant temperature is above 212*F, the reactor containment shall be monitored and recorded once every coolant leakage into the primary containment shall be 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> utilizing the Primary Containment Sump.

limited to:

Monitoring Syste~ iquipment drain sump monitoring and floor drain sump sanitoring).

a.

5 gpm unidentified leakage b.

2 gpm increase in unidentified leakage within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. (This limitation shall apply only after a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at operating pressure.)

c.

The total reactor coolant leakage into the primary containment shall not exceed 25'gpm.

I Amendment No.17. SO 102, 141

JAFNPP 4

- 3.6 (cont'd) 4.6 (cont'd) l.

2.

With reactor coolant system leakage greater than the 2.

Not Used l

limits specified in 3.6.D.1.a or 3.6.D.1.c, the leakage rate shall be reduced to within these limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the reactor shall be in at least the hot standby condition within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold condition within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.

With an increase in unidentified reactor coolant systern 3.

Not Used l_

leakage equal to or greater than the limit specified in 3.6.D.1.b, the source of the leakage shall be identified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the reactor shall be in at least hot standby condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l 4.

The Primary Containment Sump Monitoring System 4.

The Primary Containment Sump Monitoring System (Equipment Drain Sump Monitoring and Floor Drain Sump (Equipment Drain Sump Monitoring and Floor Drain Sump Monitoring ) and the Continuous Atmosphere Monitoring Monitoring) instrumentation shall be calibrated and System (Gaseous and Particulate) shall be operable when checked as specified in Surveillance Requirement 4.2.E.

the reactor coolant leakage limits of Specification 3.6.D.1 Continuous Atmosphere Monitoring System (Gaseous and are in effect.

Particulate) instrumentation shall be functionally tested and calibrated as specified in Table 4.6-2.

Amendment No. 4Ge 141a

=

JAFNPP 3.6 (cont'd) 4.6 (cont'd) 5.

With the Primary Containment Sump Monitoring System l

(Equipment Drain Sump Monitoring or Floor Drain Sump Monitoring) inoperable, restore the system 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 be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in the cold condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6.

With the Continuous Atmosphere Monitoring System (gaseous) or the Continuous Atmosphere Monitoring System (particulate) inoperable, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Amendment No. 28, SS,102,192, 142

- ~. -. -

JAFNPP TABLE 4.6-2 Minimum Test and Calibration Freauency for Continuous Atmosphere Monitorina System j.

Inst. Channel Inst. Functional Test Calibration Sensor Check-1.

Air Particle Analyzer None Once / 3 mos.

once / day 2.

Gaseous Activity Analyzer None Once / 3 mos.

once / day 3.

lodine Analyzer None Once / 3 mos.

once / day l

Amendment No. 28, 162a

, 1 to JPN-93-090 SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES RCS LEAK DETECTION LCO fJPTS-92-031) 1 DESCRIPTION OF THE PROPOSED CHANGES The proposed changes to the James A. FitzPatrick Technical Specification revise Reactor Coolant System (RCS) Specifications 3.6.D and 4.6.D on coolant leakage as addressed below.

Minor changes in format, such as type font, margins or hyphenation, are not described in this submittal. These changes are typographicalin nature and do not affect the content of the Technical Specifications.

RCS Leak Detection LCO Clarification Paae 141a. Soecification 3.6.D.4 Replace the phrase:

"during reactor power operation" with:

I "when the reactor coolant leakage limits of Specification 3.6.D.1 are in effect."

Editorial Changes

1. Paoe vi. List of Tables Delete the words "Drywell" and " Radioactivity" from the title for Table 4.6-2.
2. Pace 141. Soecifications 3.6.D and 4.6.D
a. Move Specification 3.6.D.2 to the top of the left column of page 141a and append to the remainder of the specification while replacing the following portion:

"With any reactor coolant system leakage greater than any one of the limits specified in 3.6.D.1.a or 3.6.D.1.c above" with:

"With reactor coolant system leakage greater than the limits specified in 3.6.D.1.a or 3.6.D.1.c."

b. Replace specification identifier "4.6.D" with "D."
c. In Specification 4.6.D, add a "1." to properly identify the first paragraph as Specification 4.6.D.1.

Attachm nt ll to JPN-93-090 SAFETY EVALUATION Page 2 to 6 -

3. Paos 141a. Soecifications 3.6.D and 4.6.D l
a. In Specification 3.6.D.3, replace the phrase:

"If the increase in unidentified leakage as specified in 3.6.D.1.b is exceeded" with:

"With an increase in unidentified reactor coolant system leakage equal to or greater than the limit specified in 3.6.D.1.b."

b. Renumber Surveillance Requirement "4.6.D.3" as "4.6.D.4" and relocate from page 142 to the end of the right column on page 141a. At the beginning of the specification, insert the following:

"The Primary Containment Sump Monitoring System (Equipment Drain Sump Monitoring and Floor Drain Sump Monitoring) instrumentation shall be calibrated and checked as specified in Surveillance Requirement 4.2.E."

c.

In Specification 3.6.D.4 replace the first usage of the word." primary" with

" Primary." Also in Specification 3.6.D.4, replace the words " Primary Containment Atmosphere" with " Continuous Atmosphere."

.j

d. Replace the right column heading "4.5" with "4.6."
e. Add Specifications "4.6.D.2" and "4.6.D.3" each containing the wo' ds

)

r "Not Used."

i f.

In revised Specification 4.6.D.4, replace the phrase:

"Drywell Continuous Atmosphere Radioactivity Monitoring System" with the phrase:

" Continuous Atmosphere Monitoring System (Gaseous and Particulate)."

Also in revised Specification 4.6.D.4 replace Table identifier "4.6.2" with i

"4. 6-2. "

4. Paae 142. Soecification 3.6.D in Specification 3.6.D.S replace the phrase " Primary Containment Atmosphere Radioactivity" with the phrase " Continuous Atmosphere" in two locations.

]

5. Ppae 162a. Table 4.6-2 Delete from the title the words "Drywell" and " Radioactivity."

Attachmsnt 11 to JPN-93-090 SAFETY EVALUATION Page 3 to 6 II.

PURPOSE OF THE PROPOSED CHANGES RCS Leak Detection LCO Clarification The RCS leakage detection system is comprised of the Primary Containment Sump Monitoring system and the Continuous Atmosphere Monitoring (CAM) system. The purpose of the proposed change is to eliminate an inconsistency between the RCS leakage detection and operability requirements in Limiting Conditions for Operation (LCO) 3.6.D.1 and 3.6.D.4.

LCO 3.6.D.1 currently requires that RCS leakage be below specified limits when there is irradiated fuel in the reactor vessel and reactor coolant temperature is greater than 212*F. LCO 3.6.D.4 requires the leakage monitoring systems to be operable during power operation (i.e., when the mode switch is in the Startup/ Hot Standby position or the Run position with the reactor critical above 1 percent rated power, as defined per Specification 1.0.0). Thew. two LCOs are not consistent. The proposed revision i

of LCO 3.6.D.4 will take the more conservative approach of requiring the leakage monitoring systems to be operable when the leakage limits of LCO 3.6.D.1 are in effect.

Editorial Changes The proposed changes make editorial corrections which are considered administrative in nature. These will improve the overall quality and consistency within the Technical Specifications. The purpose of each editorial change identified in Section I of this Safety Evaluation are discussed sequentially as follows:

Changes 1,3.c,3.f,4, and 5. correct the system name for the Primary Containment Sump Monitoring System and the Continuous Atmosphere Monitoring System. The renaming of the CAM system is consistent with established usage (Reference 1).

l Change 2.a relocates Specification 3.6.D.2 to line up with Specification 4.6.D.2 (inserted by Change 3.0) to be consistent with Technical Specification format between LCOs and Surveillance Requirements and makes minor editorial changes.

Change 3.a is a minor editorial change for purposes of clarification.

Changes 2.b and 2.c correct the numbering of Specification 4.6.D to be consistent with the numbering patterns used elsewhere in the Technical Specifications.

Change 3.b renumbers Surveillance Requirement 4.6.D.3 to correspond with the appropriate LCO and clarifies the Surveillance Requirement by referring to Surveillance Requirement 4.2.E. Surveillance Requirement 4.6.D.3 does not currently mention instrument calibration and checking requirements for the Primary Containment Sump Monitoring System.

Attachmsnt 11 to JPN-93-090 SAFETY EVALUATION Page 4 to 6 Change 3.d corrects an editorial error by replacing column heading "4.5" with the correct heading "4.6."

4 Change 3.e clarifies the Technical Specifications by indicating where LCOs do not have a corre.sponding Surveillance Requirement.

i 111. _ SAFETY IMPLICATIONS OF THE PROPOSED CHANGES I

RCS Leak Detection LCO Clarification The proposed changes will not require modification of any plant structures, systems or components and will not alter the conclusions of the plant accident analyses as documented in the FSAR or the NRC staff SER. Those changes will have no adverse safety implications.

The proposed changes to LCO 3.6.D.4 make the plant conditions for leakage detection system operability consistent with the plant conditions when leakage limits apply, LCO 3.6.D.1. As currently written LCO 3.6.D.4 requires RCS leakage detection systems to be operable during " reactor power operation." This would not require the systems to be operable under all conditions when LCO 3.6.D.1 requires leakage monitoring. The proposed changes have revised LCO 3.6.D.4 to refer to LCO 3.6.D.1. LCO 3.6.D.1 will require leakage oetection systems to be operable during plant conditions consistent with the Standard Technical Specifications (STS)

(Reference 2). Removal of the inconsistency provides a positive safety benefit.

i Editorial Changes These changes are administrative in nature and can have no adverse affects on plant safety. These changes will improve the overall quality and consistency within the Technical Specifications.

1 IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Operation of the FitzPatrick plant in accordance with the proposed Amendment would not involve a significant hazards consideration as defined in 10 CFR 50.92, since it would not:

1. involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed amendment involves no hardware changes, no changes to the I

operation of any systems or components and no changes to structures. It alters an LCO to require plant leakage detection systems to be operable during the same plant conditions that RCS leakage limits apply. The revised LCO requires leakage i

detection systems in operational modes consistent with other portions of the Technical Specifications. Additional changes include editorial corrections such as correct specification numbering, proper system identification, and clarification of a

Attachmtnt 11 to JPN-93-090 SAFETY EVALUATION Page 5 to 6 surveillance requirement cross reference. Since the change to the LCO for leakage detection will require operability under a greater range of plant conditions to be consistent with detection requirements, there is no change to previously determined accident probabilities or consequences. The editorial changes have no adverse safety implications.

2. create the possibility of a new or different kind of accident from those previously evaluated.

The proposed amendment involves no hardware changes, no changes to the operation of any systems or components and no changes to structures. It alters the Technical Specifications only to the extent of making two LCOs consistent by requiring the leakage detection system to be operable when leakage limits apply and making editorial changes. Editorial changes and increasiig the plant conditions for leakage system operability can not create the possibility of a new or different kind of accident from those previously evaluated since the editorial changes have no safety significance and the operability changes are being made for consistency with the modes when leakage detection is required to function.

3. involve a significant reduction in the margin of safety.

The proposed amendment revisions involve no hardware changes, no changes to the operation of any systems and no changes to structures. The revised LCO criteria for RCS leakage detection system operability has increased the plant conditions when operability is required to match the plant conditions when leakage limits apply. Editorial changes and expanded operability requirements in the LCOs will not result in any change to existing safety margins.

V.

IMPLEMENTATION OF THE PROPOSED CHANGES Implementation of the proposed changes will not adversely affect the ALARA or Fire Protection Program at the FitzPatrick plant, nor will the changes impact the environment. These changes will not result in any new releases to the environment since there are no hardware, structural, or operational changes. For these same reasons, the changes pose no radiological or fire hazards. The changes do not alter the goals or intent of the relevant LCOs or Surveillance Requirements.

VI. CONCLUSION The chariges, as proposed, do not constitute an unreviewed safety question as defined in 10 CFR 50.59. That is, they:

)

l

1. will not change the probability nor the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; L.

Attachment il to JPN-93-090 SAFETY EVALUATION Page 6 to 6

2. will not increase the possibility of an accident or malfunction of a type different from any previously evaluated in the Safety Analysis Report; and
3. will not reduce the margin of safety as defined in the basis for any technical specification.

The changes involve no significant hazards consideration, as defined in 10 CFR 50.92.

Vll. REFERENCES

1. NYPA letter, R. E. Beedle to NRC, dated September 25,1992 (JPN-92-058)

" Proposed Changes to the Technical Specifications Primary Containment lodine Monitoring Specifications (JPTS-91-006)."

1

2. NRC NUREG-1433 " Standard Technical Specifications for General Electric Boiling

)

Water Reactors (BWR/4)," Revision 0, dated September 1992.

3. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report Section 4.10.3.4, " Leakage Detection System," through Revision 5, dated January 1992.
4. James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER), dated November 20,1972, and Supplements.

m

Attachment lli to JPN-93-090 PROPOSED TECHNICAL SPECIFICATION CHANGES

' RCS LEAK DETECTION LCO fl.1ARKUP OF TEAHNICAL SPECIFICATION PAGES (JPTS-92-031) 1 1

New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59

~

JAFNPP UST OF TABLES (Cont'd)

Table Title g

42-8 Minimum Test and Calibration Frequency for Accident Monitoring 86 Instrumentation 4.6-1 Snubber Visualinspection interva.

161 4.6-2 Minimum Test and Calibration Frequency f Continuous 182a Atmosphor Monitoring System 4.7-1 (DELETED) 210 l

4.7 2 Exception to Type C Tests 211 3.12-1 Water Spray / Sprinkler Protected Areas 244j 3.12 2 Carbon Dioxide Protected Areas 244k 3.12-3 Manual Fire Hose Stations 2441 4.12 1 Water Spray / Sprinkler System Tests 244q 4.12 2 Carbon Dioxide System Tests 244r 4.12 3 Manual Fire Hose Station Tests 244s 62 1 Minimum Shift Manning Requirements 260a 6.10-1 Component Cyclic or Transient Umits 261 I

i i

Amendment No. ;p5,22, W, tri,130,1%,130,1J8,180 181 i

d i

o.

,lAPriPP 3.6 (cont'd) 4.6 (cont'd)

~

4.

Except as specified in 3.6.C.3 above, the reactor coolant water shall not exceed the following limits with steaming rates greator than or equal to 100,000 lb/hr and during reactor shutdowns.

Conductivity 5 4mho/cm Chlorido ion 0.5 ppm i

5.

If Specification 3.6.C cannot be mot, the reactor shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

-p D.

Coolant Leakaqo 4.6 D

, Co,olant Leakage P'

1.

Anytime irradiated fuel is'in the

/.' Reactor coolant leakage rate inside reactor vessel and the reactor coolant the primary containment shall be temperature is abovo 212*P, the reactor monitored and recorded once every coolant leakage into the primary con-4 hours. utilizing the Primary Con-tainment shall be limited to:

tainment Sump Monitoring System (equipment drain sump monitoring and S gpm unidentified leakage floor drain sump monitoring).

a.

g b.

2.gpm increaso'in unidentified leakage within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

(This limitation shall apply only i

after a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at oper-ating pressure.)

The total reactor coolant Icakage c.

into the primary. containment shall not exceed 25 gpm.

M With h reactor coolant system leakago 2.

M f

greater.than% uy one or the limits speci-P[f ficd in - 3.6.D.1.a or 3.6.D. l.c(abovg7the leakago rato shall be reducod to within L

these limits Amendmont-No. )T, g 102 1141

ce JAFNPP 3.6 (cont'd).

4h.5 (cont'd) l IA! SERT horn O-C

?reVtovS

&within4hoursorthere'actorshall

'b 10.4 Used h

be in at least the hot standby con-dition within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold condition within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

[jy[

tuh/, a o reae* co lanf sys*m 3.

g "I,(j,, c 3 3.

qft increase in* unidentified. leak-H a

specified in 3.6.D.1.b fis ex-J' oM A^'10 the source of the leakage shall y, Tf, (o e [ 4 [, y g f ~g,,,o

/,mih

)

_be identified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the t

/

f3+em[Evfme,gbx reactor shall be in at least hot standby A7owfor/n 7

7 condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold condition within the following 24 Emg Mo,,dern e nna F7ece Dra w G, hours.

i i

g nUc n ) ins 1cvme,vtecfic>m gfgl(

t The[rimaryContainmentSumpHonitoring fe c,g4, e[ ancp cjEc T 4.

System (Equipment Drain Sump Honitoring aF l con /mesand Floor Drain Sump Monitoring) and ec,M eg,o g ge,jf g* vee-c#

taevfrimary Contaunerrn Atmosphere Mon-

- /',2,[ f itoring System (Gaseous and Particulate)

~

. shall be operableTourina reactor power) tM5eg),e g,

y "COPeration..

d ** I*nf

' b*,lW

  • yf p,,,

& pesedce g

.qg,;,a 3X. pl are tu e ec4.

Amendment No.102 141a

l JAFNPP 3.6 (con **d) 4.6 (cont'd)

@ orywe(*t0 Continuous Atmospherdadioactisii) Monitoring n

5.

With the Primary Containment Sump Monitoring System (Equipment Drain Sump Monitoring or Floor Drain Sump System, instrumentation shall be functionally tested and d as specified in Tableh gg Monitoring) inoperable, restore the system to operable calibrate I

status 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 shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in the cold condition within

'[6as@5 and M5cv#c) s the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C'&yeu 6.

With the Pr'iim y vuin./ r.: 2 Atmosphere nav.ium.i.miy n

Monitoring System (gaseous) or the U.- ri C=::! mm C.,dmveo J Atmosphere lted:::::'My Monitoring System (particulate) inoperable, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and armlyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Otherwise be in at least hot shotdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Amendment No. ((, %, 192 142

JAFNPP e

Table 4.6-2 Continuous Atmospher oactiv fton-M,inimum Test and Calibration Frequency fo itoring System Sensor Calibration Check Inst. Functional Test Inst. Channel Once/3 mos.

once/ day None 1.

Air Partidle Analyzer Once/3 mos.

once/ day Hone 2.

Gaseous Activity Analyzer Once/3 mos.

once/ilay None 3.

Iodine Analyzer E

J Amendment No..28

.

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