Text

Proposed Tech Specs Incorporating Operating Requirements of post-accident Monitoring Instrumentation
	ML19325E485
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	10/31/1989
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML19325E481	List: ML19325E480; ML19325E485;
References
	NUDOCS 8911070220
	Download: ML19325E485 (28)
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3; SUkVEILLMcCE LIMITIleG C3GITIWt FWt OPERATION REDUIRDEltT

FAJE 3.7 Steam Generator Emergency Heat Removal

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-l'56 3.7.1 Steam Generator Safety valves 4.7.1 156 3.7.2 Auxiliary Feed = ster Pump System 4.7.2 158 3.7.3 Auxiliary Fr%ter Supply System 4.7.3 159a Bases 3.8 Erwrgency Core Cooling and Core Cooling Support 4.8 164 3.8.1 Centrifugal Chargin; Pump Systre 4.8.1 164 3.8.2 Safety Injection Pug System 4.8.2 168 3.8.3 Residual Heat Removal Pump system 4.8.3 170 3.8.4 System Testing of Centrifugal Charging. Safety 4.8.4 173 Injection, and Residual Heat Removal Pump Systems 3.8.5 Accumulator System 4.8.5

-174 3.8.6 Component Cooling System 4.8.6 -

175 3.8.7 Service W ter Systee 4,9.7 178 3.8.8 Hydrogen Controi Systees 4.C.8 ISO 3.8.9 Accident Monitoring Instrumentation 4.8.9 184 3.9 Containnent Isolation Systems 4.9 197 3.9.1 Isolation valve Seal idater System 4.9.1 197 3.9.2 Penetration Pressurization Systems 4.9.2 196 3.9.3 Containa nt Isolation Valves d.9.3 199a 3.9.4 Main Steam Isolation Valves and 8ypasses 4.9.4 200 3.9.5 Containment Integrity 4.9.5 201 Bases 3.10 Containment Str r-tural Integrity 4.10 212 3.10.1 Containment Leakage Rate Testing 4.10.1 212 3.10.2 Containment Air Locks 4.10.2 214e 3.10.3 Containment Tendons 4.10.3 215 3.10.4 End Anchorages and Concrete 4.10.4 217

[,s.

3.10.5 Containment Pressure 4.10.5 219 3.10.6 Containoant Temperature 4.10.6 219 Bases 3.11 Radioactive Liquids 4.11 222 Bases 3.12 Radioactive Gases 4.12 230 Bases iii TSC 89-11

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5.2 Re:w tor Coolarrt System...............................

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5.4 Containment System..........

.3,j 298

5i 5.5 Fuel Storag: .

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5.6 Seismic Deitgn...;...............................

.Q M1

-ga MI 300

.D 6.0 8(MINISTRATIVE CORIHOLS.................................

i1 300

',Y; 6.1 Organization. Review, Investigation end Audi t.................... -

2:q 308 (dj1 6.2 Plant Operating Procedu es.............................

W E.h 6.3 Actions to be Taken 1 the event of a Reportable 310 Event in Plant Operation Q

$f 311 l

'M 6.4 Action to be Taken in the Event A Safety Limit is Exceeded l

311 M3 6.5 Plant Operating Records...............................

g:j 3

312 S

6.6 Reporting Requirements..........

325

.. a 6.7 Offsite %se Calculation Manual (00CM)............

-4.h 326

g j 6.8 Flooding Protection N

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4 LIMITING CONDITION FOR OPERATT9N SURVEILLANCE REQUIREMENT I

%f 3.8.9 The accident monit<--ing instrumantation 4.8.9.

Each accident monitoring instrumentation-

.M channels shown in Tasle 3.8.9-1 shall be channel shall be demonstrated OPERA 8tE by

[d OPERABLE.

performance of the CHANNEL CEECK and Instrument

'd CHANNEL CALI2PATION operations at the-f:5 APPLICABILITY: P9 DES 1, 2 and 3 frequencies shown in Table 4.8.9-1.

qh ACTICM:

a.

hith the number of OPERABLE accident b1 monitoring instrument channels less than

' $j the heguired Number of Chanr.els sNnen in i;;L Table 3.8.9-1, (Col. 2), either restore W

the inoperable channel (s) to OPERABLE

! 8) status within 7 days, or be in at least

i MODE 4 within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .*

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b.

With the number of OPERABLE accident F9 monitoring instrumentation channels less g;

than the Miulmuu1 Channels Operahlt requirements of Table 3.8.9-1, (Col. 3),

' y either restore the inoperable channel (s) h to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or be A

in at least MODE 4 within the next 12

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hours.

d j

c.

The provisions of Specifications 3.0.4 are j

not applicable.

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This action does not apply to the PORY Position pl Indicator or the PORY Block Valve Position d'3 Indicator if the Block Valve on the associated P

line is known to be closed either by verification fjj within 7 dafs or by system status knowledge prior

j to indication failure.

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1. Containment Pressure (Marrow Range)

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2. Containment Pressure (Wide Range)

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3. Reactor Coolant Outlet Temperature - Tg (Wide Range)

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4. Reactor Coolant Inlet Tyrature - T g (Wide Range) h R

5. Reactor Coolant Pressure (Wide Range)

M-R

6. Steam Line Pressure M

R a

7. Pressurizer Water level M

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8. Steam Generator Water Level (Marrow Range)

M R:

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M R

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13. PORV Position Indication M

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17. Containment Water Level (Nrrow Range. Wide Range and Sump Lights)

M R

18. Reactor Vessel Water Level M

R M: Monthly R: Refueling Accident Monitoring Instrumentation Surveillance Repirements I

Table 4.8.9-1 192b T5C 89-11 Sh'*e=*'*"h-+

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ACTION 4 - With the nus6er of OPERABLE channels les; than the mid mum number required, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per shif t and these samples are ana'yzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . In addition, initiate an alternate method (if -

4 feasible) of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1.

Either restore the inoperable Channel (s) to OPERABLE status within 7 days of the event, or

2. ' Conduct a Station Review within 14 days fo? lowing the event, cuttining the action taken, the cause of the inoperability and the planned schedule for restoring the system to OPERABLE status.

ACTION 5 - With the number of channels OPERABLE less than the minimum number required, the contents of the tank may be released to the environment provided that prior to initiating the release:

1.

At least tw independent samples of the tank's content are analyzed, and 2.

At least two technically qualified mem6ers of the facility staff independently verify the release rate calculations and discharge flow path valving; otherwise suspend release of radioactive effluents via this pathway.

ACTION 6 - With the number of channels OPERABLE 1ess than the minimum nos6er required, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per shif t and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 7 - With the number of channels OPERABLE 1ess than the minimum number required, and no redundant monitor OPERABLE in this flow path, issuediately suspend PURGING of radioactive effluents via this pathway.

ACTION 8 - With the number of channels OPERABLE 1ess than the minimum nu4er required, effluent releases via this pathway may continue for up to 30 days provided savles are continuously collected with auxiliary sampling equipment as required in Table 4.12.1.

ACTIGil 9 - With the number of OPERABLE channels less than the minimum number reovired, effluent releases via this pathway may continue provided the flow rate is estimated at least once per shif t while release is in progress.

ACTION 10 - With the number of OPERABLE channels less than the minimum num6er required, initiate an alternate method (if feasible) of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1.

Either restore the inoperable Channel (s) to OPERA 8tE status within 7 days of the event, or 2.

Conduct a Station Review within 14 days following the eveet outlining the action taken. the cause of the inoperability and the planned schedule for restoring the system to OPERABLE status.

ACTION 11 - With the number of OPERABLE channels less than the minimum number required, suspend vent and purge operations and cir,se each vent and purge valve prcviding direct access from the containment atnesphere to the outside atmosphere or suspend the move==

of nuclear fuel and reactor components in the vicinity of the reactor, refueling cavity, and transfer nal (containment side).

ACTION 12 - With the number of OPERA 8LE channels less ' *an the minimum number required, ef fluent releases via this pathway may continue provided the effluent flow is being accounted for in the total plant effluent.

R dinar.tive Gateous Effluent Monitor Instrume2tation (Conti_nuedl 4

Table Notation Table 3.12-1 (Continued) 237 T5C 89-11

/sc1:0357T:26

?

. -. 3 Action 27:

With the number of channels OPERABLE less than the minimum number required ef fluent via this pathuy J

may continue provided the gross radioactivity level (beta /gasus or isotopic) is determined at least once '

per day. If the inoperable channel is not returned to OPERASLE status within 30 days conduct a Station Review to determine a plan of action to restore the channel to operability.

Action 28:

With the nus6er of chaenets OPERABLE 1ess than the minimum num6er eeguired, comply with the surveillance requirements 4.3.3.A.2 and 4.3.3.8.

Action 30:

With the nus6er of OPERA 8LE channels less than the minimum number required, initiate an alternate method (if feasible) of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1)

Either restore the inoperable Channel (s) to OPERABLE status within 7 days of the event, or 2)

Conduct a Station Review witt!.14 days following the event outlining the action taken, the cause of the inoperability and the planned schedule f er restoring the system to OPERABLE status.

R_adiation Monitorina Instrumentation (Continued 1 Table Notation (Continued)

Table 3.14-1 (Continced) 252a TSC 89-11

/sc1:0357T:27

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761

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LIMITING CONDITION FOR OPERATION

- SUAVEILLANCE REQUIREMENT y

@ff 3.17 Yent11ation 4.17 Ventilation

$1 21 3.17.1 applicability 4.17.1 Applicability M

Applies to the testing of particulate filters and Applies to the testing of particulate filters and -

$g%

[

S charcoal adsorbers in safety-related air charcoal adsorbers in s'.fety related air j,9 filtration systems.

flitration systems.

-fy j?

Obiective Obiective 2s

$j To verify that leakage efficiency and lodine To verify that leakage efficiency and iodine j:q removal efficiency are within acceptable limits.

removal efficiency are within acceptable limits.

e.]

@k Specification Specification 4

5%

Safety-related ventilation filters shall be ya periodically tested.

A.

The control room makeup air charcoal adsorbers A.

The control roon makeup ciiarcoal adsorber system shall be OPERABLE at all times, exctpt system shall be demonstrated OPERABLE:

l h

g) g as specified in 3.17.1.B.

W 1.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying 7

$l 8.

From and after the date that the ccntrol room that the control room air temperature is less than or equal to 90*F, and pjj makeup air charcoal adsorber system is made or M

found inoperable for any reason, restore the

?N system to OPERABLE status within 7 days or be 2.

At least once every 31 days, the control

.E in at least MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and room charcoal booster fans shall be g

in MODE 5 within t!'e following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

started from the control room.

Perforr ece will be acceptable, if the fj fan s'ei ** rpon actuation and directs air Q

throq4 W charcoal adsorbers and n

operatM ior at least 15 minutes.

h:g{

B.

Not Applicable.

uS

MaG 11879/11880 281 TSC 89-11 f{5 3

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Basis:

f.d 3.17' ihe plant ventilation systems are described in Reference (1). The filters listed in Tables 4.17-1 and 4.17-2: -

p.32 serve the Auxiliary Building, the Fuel Building, the Control Room and the containment ventilation systems.

.w (h

All ezhaust air from the Auxiliary fia11 ding and Fuel Building will be routec through HEPA (high efficiency air

(

4.fyp particulate) filters. Exhaust air from areas which may be contaminated by iodir.e are alss filtered by charcoal if high radiation levels are detected.

fM i

The OPERABILITY of the control room ventilation system ensures that 1) the ambient air temperature does not

$pI exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by.

r[

3(

this system and 2) the Control Room will remain habitable for operations personnel during and following all Ly.

credible accident conditions.

h The Contro) Room air is automatically routed through HEPA and charcoal filters, if high radiation is detected.

Ig 4

T4 The containment purge exhaust air is always routed through HEPA filters. ~

3 A.4$j The containment circulating air is routed as necessary through the HEPA filters and charcoal filters of the jg charcoal fans prior to personnel access or containment purging.

45 The aircraft fire detection system is desioned to mitigate the consequences of an aircraft crash into the areas C@j of ventilation ducts where the effects of a fire from the aircraft fuel could affect operation of plant

q equipment necessary for plant shutdown. This system is designed to prevent flames and fuel from entering the jyj ventilation duct system.(2)

L.

(f'1 Sl (1) FSAR Section 9.10 7'

(2) FSAR Section 2.2E wl j;

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11870/11880 287 TSC 89-11 (4

0837A/0839A

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(6.2.

Plant Goeratina Procedures o

. ritten procedures including applicable checkoff lists' covering items listed below shall be prepared, W

1.

- implemented, and maintained:

- Normal startup, operation,- and shutdown of the reactor acd other systems and components involving A.

f nuric safety of the facility.

l B.

Refueling cperations.

t_

Actices to be taken to correct specific and foreseen potential malfunctions of systems or components C.

ir. clue,ing responses to alarms, suspected primary system leaks, saJ abnormal reectivity changes.

l Emergency conditions involving potential or actual release of radioactivity

" Generating Stations D.

l Emergeicy Plan" and station emergency and abcormal procedures.

l Instrunentation operation which could have an effect on the safety of the fac81ity.

E.

I Preventive and corrective maintenance operations which could have an effect on the safety of the f

F.

j facility.

I l

G.

Surveil"ance and testing requirements.

l H.

Tests and experiments.

t I.

Procedures to ensure sai; shutdown of the plant.

J.

Station Security Plan and implementing procedures.

K.

Fire Protection Program implementation.

Post Accident Sampling Program which will cnsure the capability to: obtain and analyze reactor coolant L.

and containment atmosphere samples, collect and analyze or meascre radioactive iodine and particulates in plant gaseous effluents under accident conditions. The program shall include the following:

(i) Training of personnel, (ii) Procedures for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment.

Working hours of the Shif t Engineer, Shif t Control Room Engineer, Shif t Foreman, and Nuclear Station M.

Operator such that the heavy use of overtime is not routinely required.

TSC 89-11 309-I L

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.r 6 d (Continued)-

- 2.

Radiation control procedures shall be prepared implemented and maintained. These procedures shall specify.

The permissible radiation exposure limits and shall be consistent with the requirements of 10CFR 20.

radiation protection program shall meet the requirements of'10CfR 20.

Procedures for items identified in Specification 6.2.1 and any changes to'such procedures shall be reviewed 3.

and approved by the Operating Engineer and the Technical Staff Supervisor in the areas of operation and fuel handling, and by the Maintenance Assistant Superintendent and Technical Staff Sepervisor in the areas of Procedures for items identified in plant maintenance, instrument maintenance, and plant inspection.

Spacification 6.2.2 and any changes to such procedures shall be reviewed and approved by the Technical Staff Supervisor and the Health Physics Supervisor / Chemistry Supervisor or designees. At least one person In addition, approving each of the above procedures sna11 hold a valid Senior Reactor Operator's license.

these procedures and changes thereto must ha,e the authorization of the Station Manager or designee before being implemented.

b Work and instruction type procedures which implement approved maintenance or modification procedures shall be approved and authorized by the Production Superintendent. The " Maintenance / Modification Procedure" utilized for safety related work shall be so approved only if procedures referenced in tha " Maintenance / Modification Procedure" have been approved as required by 6.2.1.

Procedures dich do cot fall within the requirements of 6.2.1 or 6.2.2 may hc approved by the Department Heads.

Temporary changes to orocedures identified in Specifications 6.2.1 and 6.2.2 above may be made provided:

4.

A.

The intent of the original procedure is not altered.

The change is approved by two mead >ers of the plant management staff, at least one of whom holds a Senior B.

Reactor Operator's t.icense on the unit affected.

The change is documented, reviewed by the Onsite Review and Investigative Function and approved by the C.

Station Manager cr designee within 14 days of implementation.

Drills of the emergency procedures described in Specification 6.2.1.D shall be conducted at the frequency 5.

specified in the Generating Station Emergency Plan. These drills will be planned so that during the course of the year, communication links are tested and outside agencies are contacted.

6.3 Action to be Taken in the Event of a Recortable Event in Plant Operation:

Any Reportable Event shall be proeptly reported to the Vice President Pwt Operations or his designated alternate.

The incident shall be promptly reviewed pursuant to Specification 6.1.7.B.2.(j) and a separate report for each reportable event shall be preparad in ar ordance with the requirements of 10CFR 50.73.

310 TSC 89-11

2.

5,>

..+

AUACHMERLl ZION NUCLEAR POWER STATION nc+

ER0EQSED CHANGES TO TECHNICAL SPECIFICATIONS AEEENDIX A NUREG 0737 RE0utREMENIS DESCRIPTION /JUSJIFICATION 0F PRQEQSED_ CHANGES 4

i )

+

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Distriat10ILansLJuttification of Citattges Page ti1:

j s.

.c

.a)

Item 3.8.9 -

revised title from " Equipment for Evaluating Post LOCA" to " Accident Monitoring L'

Instrumentation" to be consistent with w

Standard Tech Specs, b

Page'v:

j a) ' Item 6.4 ar,d 6.5 -

revised page number from 310 to 311.

Pages were not I

revised with Amendment 115/104.

Page X:

1 a)

Item 4.8.9 revised page number from 192b to 192c.

Required since new page added for accident monitoring table.

V Page 184:

a)

Item 3.8.9 ACTION a:

revised to be consistent with NUREG 0737 and Standard Tech Specs.

b). Item 3.8.9 ACTION b:

revised to be consistent with NUREG 3737 and Standard Tech Specs.

je l

c). Item 4.8.9:

changed 3.8.9 to 4.8.9 (typo) and revised requirement to be consistent with NUREG 0737 and Standard Tech Specs.

d)

Note -

changed " Indication" to " Indicator" similar to Table 3.8.9-1.

g Pags-192a:

i a) Column'3 - changed title to be consistent with NUREG 0737, Table 3.3-10.

I i

l b)

Item,1 -

added Containment Pressure (Hide Range) to the total number of Containment Pressure Channels.

Bc:a narrow and wide range containment pressure instruments meet the requirements of Reg u

Guide 1.97, Rev. 3.

c)

Item 10 - added " Rate" to noun name to more clearly define the parameter as described in NUREG-0737, Table 3.3-10.

1 l

d 1

l

/sc1:0357T:4 e

2 a

y --

n -

~

LM L'.

, _ (Continut_dl

[

d) ' Items:11-revised Total Number of Channels of PCS subcool,ng to 3 F

channels, since there are 2 channels of installed subcooling instrumentation and one a6ditional channel that can be

?

considered by procedurally calculating RCS >ubcooling using

[

inputs from RCS wide range pressure instrumentation and Average f-of the 10 Highest Core Exit Thermocouples or the highest RCS Hot leg temperature.

Page 1925:

c a)

Item 12 - changed " Indication" to " Indicator' per NUREG 0737, Table 3.3-10 b)

Item 13 - changed " Indication" to " Indicator" per NUREG 0737, Table 3.3-10.

c)

Item 14 - changed " Indication" to " Indicator" per NUREG 0737, Table 3.3-10.

d) Item 15 - added now instrumentation "Cors Exit Thermocouples" as required by NUREG.0737 Item II.F.2.

Instrumentation hes been approved by letter from S. A. Varga (NRC) to D. L. Farrar (CECO) dated August 18, 1986.

e)

Item 16 - added new instrumentation " Containment Water Level (Narrow u

Range) and Containment Recirculation Sump Lights" as required by NUREG 0737 Item II.F.1.5.

Note:

There are 2 contatriment water level nerrow range channels that monitor the Containment Sus and 2 channels of Containment Rerkculittion Sump tndicating lights that monitor the Containment Recitculation Sump water i

level.

It is recommended that the Containment Retir_culation Supp indicating lights be considered as two additional channels of Containment Water Level (Narrow Range) instruments. This is because the Containment Recittulttion Sus lights overlap the total indicating range of the Containment Snep water level instruments.

Added # note to table 3.8.9-1 for this item.

Note allows for oper6 tion up to 30 days with less than the specified number of channels OPERABLE.ptr NUREG 0737, Table 3.3-10.

f) Item 17 - added new instrumentation " Containment Hater Level (Hide Range) l as required by NUREG 0737. Item II.F.1.5 and Table 3.3-10.

Added ## note to table 3.8.9-1 for this item.

Note allows for operation up to 30 days with less than the minimum channels operable, provided at least one channel of Containment Etc.lr_culation Sump level Indicating lights and one channel of Containment Sump water level are operable.

See item k) on ##

Note.

g)

Item 18 & 19-added new instrumentation " Reactor Vessel Water Level" per NUREG 0737, Item II.F.2.

The system is a differertlal pressure measurement system designed by Hestingho3se.

Item 18, Reactor Ves:e1 Hater Level (Hide Range) requires at least one reactor coolant pump (RCP) running to provide reliable indication.

Item 19, Reactor Vessel Hater Level (Harrow Range) requires all RCPs to nel be running in order to provide reliable indication.

Added ### note to Table 3.8.9-1 for this item.

L

'/sc1:0357T:5

h q

l Ma ;

t, AltAchment 2 (Contir)uedi yw MM' h)

Note -

added numbers of' channels to each method of monttoring PCS

' Q>.

subcooling.

a E

1) ** Note -~ revised note to change " Indication" to " Indicators".

a v

j) # Note -

revised note to be consistent with NVREG 0737, Table 3.3-10.

t) ## Note - note allows for continued operation for up to 30 days with Contal.. ment Water Level (Hide Range) less than Minimun Channels Operable provided at least one set of Containment Etcits.ulation Sump indicating lights and one channel of Contair, ment Water Level (Narrow Range) instruments are operable.

The basis for this deviation from NUREG 0737 requirement of 7 days is because the Containment Hater Level (Hide Range) instruments are located i

inside containment but outside the missile barrier.

The instrument sensing lines are cil filled and would require draining, evacuating and refilling the lines after rtpairs are

. completed by the vendor.

It would be difficult to accc'nplish repairs within 7 days.

Hith two trains of independent containment water level (narrow range) instruments operable, i

L identification of an abnormal increase in containment water L

level during this period of time should be considered as acceptable.

1)' ### Note - note allows for continued operation with either Hide Range or Narrow Range instruments less than Minimum Required Operable, prov'ided Core Ex1t Thermocouples and RCS Subcooling Margin instruments are operable. In addition, a Station Review must be conducted within 7 days to determine the cause of inoperability, h

plan of action to take and schedule for restoring the system to opereble status.

This note is justified by lettar from S. A.

Varga (NRC) to D.L. Farrar (CECO) dated August 18. 1986.

Since th9 Zion Station Emergency Operating Procedures are written allowing for use of the Reactor Vessel Water Level System or io Core Lxit Thermocouples in the detection of an inadequate core cooling condition, the unit may continue operation until repairs I

can be, accomplished on the system.

It would require the unit tc be placed in the Cold Shutdown condition with the Reactor Coolant System depressurized to allow realignment of the Reactor i

l Vessel Water Level System following isolation and repair of an instrument sensor.

p, Page 192c a)

Item 1 - added Containment Pressure (Hide Range) to allow for additional y

qualifted instruments to be used for monitoring containment pressure during accident conditions.

ff b)

Item 10 - added " Rate" to noun nana to more clearly define parameter as L

described in NUREG 0737, Table 4.3-7.

c) Item 12 - changed " Indication" to " Indicator" to be consistent with NUREG 0737, Table 4.3-7.

d)

Item 13 -- changed " Indication" to " Indicator" to be consistent with NUREG 0737, lable 4.3-7.

/scl:03S7T:6

9 (Continued)-

,s q

4 0 e)

Item 14 - changed " Indication" to " Indicator" to be consistent with NUREG 0737, Table 4.3-7.

f)~ Item 15 - added new item " Core Exit Tnermocouples" as required by NUREG 0737, Table 4.3-7.

g)

Item 16 - added new item " Containment Hater Level (Narrow Range) and Containment Recirculation Sump Lights" as required by NUREG 0737 Table 4.3-7.

h)

Item 17 - added new item " Containment Nr.ter Level (Hide Range)" as required by NUREG 0737, Tabic 4.3-7.

1)

Item 18 - added new item " Reactor Vessel Hater Level (W'de range)" as required by NUREG 0737, Table 4.3-7.

j)

Item 19 - added new item " Reactor Vessel Htter Level (Narred Range)" as required by NUREG 0737 Table 4.3-7.

Page 195:

a) Capi.talized definitions "0PERABILITY", "0PERATING", " CHANNEL CALIBRATION" and " REFUELING CYCLE" to be consistent with Tech Spec requirements for l

definitions.

b) Added NRC Generic Letter 83-37 to last paragraph to identify recommendation for NUREG-0737 Technical Specifications and also dates of referenced documents.

Page 236a:

a) -Items 4.A.4 and 4.A.5 Action statements have been changed fiom Action statement 6 to'new Action statement 4 on Page 237.

l Page 237:

a) Added new Action statement 4 :,imilar to NUREG 0737, Enclosure 3 Model Tech Spec Table 3.3-6, Action 30.

However, action statement retains current requirement of Action 6 which allows for effluent releases via this pathway for up to 30 days provided grab samples are taken at leest onct per shift and analyzed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for gross activity, b) Revi' sed Action statement 10 to be timilar to NUREG 0737, Enclosure 3 Model Tech Spec Table 3.3-6, Action 30, with the following difference. A Station Review will be conducted within 14 days following the event versus submitting a Special Report to the Commission within 14 days of the event.

This exception from the samnle Tech Spec is requested since the condition will be reportable under the LER program per 10 CFR 50.36(c)(2) and 10 CFR 50.73, if the action statement is exceeded. Duplicate r porting requirements is an unnecessary admin?strative burden.

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' (Continued)_

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Page 252,a:

a) Action 30:

Revised to be' consistent with the requirement of GL 83-37, Model Tech Spec Table 3.3-6, Action 30.

This change is the i

same as Action statement 10 on Page 237.

)

l Page 281:

a) Revised Technical Specification 3.17.1.A to control room make'Jp air charcoal absorber system to be OPERABLE at all times.

b) Revised Technical Specification 3.17.1.B to capitalize "0PERAELE" and l

change " hot shutdown" to "HODE 2" and " cold shutdown" to " MODE 5" to be consistent with other recent Zion Tech Spec Changes.

.c) Revised Surveillance Requirement 4.17.1.A to include verifying control room air temperature is less than or equal to 90'F every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months The limitation of 90'F has been determined to be an upper limit for personnel habitability requirements and control room equipment operation.

This limit is the saine as that approved for Commonwealth Edison's, Byron and Braidwood Station Technical Specifications.

.Page 287:

a) Adbed statement on control room ventilation system to ensure 1) that ambient air temperature does'not exceed allowable temperature for equipeent an1 instrumentation and 2) control room will remain habitable for operations personnel during e.nd following all credible accident conditions.

Page 310:

No Changes - Items from page 309 shifted to page 310.

a) Item 6.2.1.L-revised to add requirements of Post-Accident Sampling Program as per NUREG 0737, Item II.B.3 and GL 83-37, Enclosure 3.

This change also incorporates requirements of item II.F.1.2, (Sampling and I'-

Analysis of Plant Effluents).

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ATTACHMENT 3 ZION NUCLEAILf0REfLS.TAIloti O.

.. t ER0fDSED CHAPGES TO TECHNICAL SPECIFICATI0RS

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APPENDIX A HUREG_0737 RE01IIREMENTS-t M LUATION OF SIGNIFICANT HAZARDS f

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8tikchment_3 EV A.l u allon.0LSignifita aUlmtdLConsidention l

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,This proposed license araendment involves changes that must be evaluated for.no 1significant hazards consideration.

The changes consist of the following items:

1 1

1) Addition of Containment Pressure (Hide Range), Core Exit Thermocouples,

)

Containment Hater Level (Narrow and Hide Range) and Reactor Vessel Hater

)

Level (Narrow and Nide Range) instrumentation to Technical Specification 3/4.8.9, Accident Monitoring Instrumentation, Tables 3/4.8.9-1.

j

2) Revision of action requirements f or inoperable Noble Gas Effluent Monitors in Technical Specifications 3/'4.12.3, Radioactive Gaseous Effluent Monitor 1

Instrumentation Table 3.12-1, 1

3) Revision of 3ction requirements for inoparable Containment High-Range Radiation Monitors in Technical Specification 3/4.14.1, Radiation Monitoring Instrumentation, Table 3.14-1.

4)

Inclusion of control room air temperature limitation into Technical Specification Surveillance Requirement 17.1.A.

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S) Revision of Post-Accident Sampling Program Administrative Technical Specification 6.2.1.L to include spec!fic requirements of the program.

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10 CFR 50.92 states that a proposed amendment will involve a no i

significant hazatds consideration if the proposed amendment does not:

1)

Involve a significant increase in the probability or consequences of an accident previously evaluated; or

'2)

Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3)

Involve a significant reduction in a ;.argin of safety.

The discussion belos addresses e4 h 9 these three criteria and demonstrates that the proposed amendm mr.nvolves a no significant hazards consideration.

Item 1.

This proposed change is being made in accordance with Generic Letter 83-37 which identifies items from NUREG 0737 that are required to be included in our Technical Specifications.

The additional instrumentation being added to the Accident Monitoring Instrumentation System i.e.; Containment Pressure (Hide Range), Core Exit Thermocouples, Containment Water Level (Narrow and Wide Range),

and Reactor Vessel Hater Level (Narrow and Hide Range), will pro /ide

. c additional indication to aid in identifying degraded core conditions.

The additicn of these instruments will enhance response to accidents as evaluated in the Final Safety Analysis Report and i

thus will not involve a significant increase in the probability or consequences of any accident previously analyzed.

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,,'o A11Athment 3 (Continuedl The addition of a control room air temprature limitation in Technical Specification 4.17.1.A, will et,sure that action is taken to maintain the control room environment habitable for operators during all plant conditions.

This change will not 9mpact on any accident analysis addressed in the FSAR.

Changes to the requirements for inoperable containment high range area radiation monitors, noble gas effluent radiation monitors and steam generator atmospheric relief and safety valves radiation monitors have been made more conservative.

They do not impact on any accidents previously analyzed in the FSAR, Clarification of the Post-Accident Sampling Program is an administrative change and does not affect any accidents previously analyzed.

Item 2.

The instrun.ents added to the Accident Monitoring Ins +rumentation System will be used to improve the identification of plant conditions during and after an accident has occurred.

In addition, changes to the Technical Specifications for the radiation monitoring system, control room environuent and post-accident sampling program will enhance overall plant operations.

These changes diso will not have an effect on the generation of any external event such as earthquakes on tor nadoe s.

Thus, the.v do not create the po:sibility of a new or different kind of accident than any previously evaluated for Zion Station.

Item 3.

As discussed above, this proposed amendment will upgr de the Accident Monitoring Instrumentatio' System, Radiation Monitoring System, Control Roon Ventilation Systen and the Post-Accident Sampling Program at Zion Station.

Thus the additional requirements in this proposed amendment increases the margin of safety at Zion St6 tion.

The proposed changts of this amendment are intended to upgrade the requirements of the accident Monitoring System, Radiation Monitcring System, Control Room Ventilation System and the Post-Accident Sampling Pronram.

Thus, example (ii) is atplicable in this instance.

Example (ii) states:

(ii) A change that constitutes an additional limitation, restriction, or control not presently included in the Technical Specificetions; for example, a more stringent surveillance requirement.

Therefore, since the application for amendment satisfies the criteria specified in 10CFR 50.92 and is similar to an example for which no si 91ficant hazardt consideration exists, Commonwealth Edisor Company has made a determination that the amendment involves no significant hazards consideration.

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P A.laCHMERI__4 I

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a STATUS OF GENERIC LETTER 83-37.

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ERCLOSURE 1. ITEMS 1

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StA1115_Qf _GentricltlitLal-37 Enc 1olure 1 Itemi

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Item (1)

Reas. tor __ Coolant system vents (II.aal

)

2

Response

Item is addressed by current Technical Specifications 3/4.").I.G.

and Bases 3/4.3.1 which was approved by Technical Specification

',c Amendments 86 and 76 for Unit I and Unit 2 respectively.

Reference:

letter for S. A. Verga 'NRC) to D. L. farrar (CECO)

L dated September 9, 1983.

/

Item (2)

Enstaccident_. Sampling (II.B.21

Response

Item is addressed by revising current Technical Spicification 6.2.1.L Post-Accident Sampling Program to describe what has to be sampied and analyzed under accident condition; The change alsc-includes requirements of the program, such a,:

a) training of personnel, b) procedures for sampliieg and analysis, and c) provisions for maintenence of sampling and analysis equipment.

The change is similar to GL 83-37, Enclosure 3, Model Tech Spec 6.8.4.

Item (3)

.Long.ltrt_ Mix 1.liary Feedwater System Evaluation (II.E.1.1)

Responie:-

Item is addressed by current Technical Specification 3/4.7.2 and Bases */4.7. which was approved by Technical Specification Amendment 80 and 70 for Unit I and 2 respectively.

Reference:

' letter from S. A. Varga (NRC) to L. O. DelGeonge (CECO) dated

' January 21, 1983.

Item (4)

Hoble Gas-Efflugnt Monilors_JII.F.1.1)

. Response:

Item is addressed by revising current Technical Specification 3.12.3.A, Table 3.12-1.

Change will be similar to GL 83-37,, tiodel Tech Spec 3.3.3.1, Table 3.3-6 Action Item 30, with the exception of requiring a Station Review to be performed within 14 days in lieu of a Special Report.

Item (S)

S.ampling_And_ Anc_1ysis of._ElAQtlfflugnts (II.F.1.21

Response

Item is addressed by incorporating requirements into the Post Accident Sampling Program as addressed in Item (2) above by utilizing GL 83-37, Enclosure 3, Model Tech Spec 6.8.4.

Item (6)

Contalng at High-Range Radiat10D_Sonitor (II.r.l.3)

Response

Item is addressed by revising Action item 30 of Technical Specification 3/4.3.14 Plant Radiation Monitoring, Table 3.14-1.

Change will be similar to GL 83-37, Enclosure 3, Model Tech Spec 3.3.3.1, Table 3.3-6 Action 30 with the exception of requiring a Station Review to be performed within 14 days in lieu of a Special Report.

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Item (7).

Contdnment Pres.s.ute MxtLtor.(II.F.1.41

Response

Itam is addressed :y revising current Technical Specification

.t/4.8.9 Table 3.8.')-1.

Containment Pressure (Hide Range) will i5 be added to the total number of Containment Pressure Channels.

l Both Na. row Range and Hide Range instruments meet the I

requirements of Re; Guide 1.97, Rev. 3.

I Item (8)

C9AtAIDmen Unnifr_ evel Monitor (II.F.1.51

Response

Item is addressed 'ay incorporating requirements into the j

Acciden+ Monitorin; Instrumentation Technical Specification as described in GL 83-37 Enclosure 3.

However, Containment i

Recticulation Sump Level Indicating Lights are being added as 2 l

l additional Containinent Witer Level (Harrow Ranga) instrument

)

channels.

Item (9)

Contdemant Hydroatn Bonitor_!II.F.1.6)

Response

Item is' addressed in Technical Specification 3/4.8.8.8, per Technical Specification Amendm0nt 07 and 77 for Unit I and Unit' 2 respectively.

Reference:

letter from J. Norris (NRC) to i

D. L. Farrar (CECO) dated March 14, 1985.

~

Item (10)

Instrumentation fo* Detection of Inadeauate Core Cooling (II.F.2)

Response

Item is addressed by incorporating into Technical Specification i

3/4.8.9, Tables 3.d.9-1 and 4.8.9-1, Core Exit Thermocouples and j

Reactor Vessel Hater Level instruments.

In addition, RCS

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Subcooling Margin monitors are being rev; sed to identify a total of 3 channels. This instrumentation has been previously l

approved for use :n the detection of inadequate core cooling by letter from S. A. '/arga (NRC) to D. L. Farrar (CECO) dated August 18, 1986.

Item (l1)

ControLBoomJiablinh1111yJesultemenis_U 1 LA3,M I

Response

Item is addressed and found acceptabl3 by the Commission per letter from S. A. Varga (NRC) to L. O. De1 George CECO dated June 24, 198"..

Control room temperature limitation requirements have i

been ir.cluded in Technical Specification 4.17.1.A.

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ML19325E485

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