Text

Proposed Tech Spec 3.3.3.6 & Tables 3.3-10 & 4.3-7 Reflecting Reg Guide 1.97 Reviews
	ML20153E959
Person / Time
Site:	Mcguire, Catawba, McGuire, 05000000
Issue date:	05/04/1988
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20153E943	List: ML20153E940; ML20153E959;
References
	RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8805100188
	Download: ML20153E959 (26)
	v • d • e

. _ _ _

ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION AMENDMENTS 8805100188 880504 PDR ADOCK 05000369 P DCD

INSTRUMENTATION

( ACCIDENT MONITORING INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION :

l 3.3.3.6 The accident monitoring instrumentation ch&nnels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION: !

a. With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With the number of OPERABLE accident monitoring instrumentation channels ex::pt th: unit ; nt-high-high r:ng; e,:: ;; nit:r, th-

t::: relief v:1v: : h: :t radiati:n :: nit r, th: : nt:fr::nt

- te::ph:re-high rang; radicti:n ;rit:r, :nd the re::ter 00!:^t r:dicti:r 1:;;l less than the Minimum Channels OPERABLE requirements of Table 3.3-10, restore the inoperable channel (s) to OPERABLE status

(- within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STAN0BY vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUT 00WN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

,__ ..:. : _ m _ u _ u _-

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" r - - ,. Or : riter,

rib: :h: :nt:i=:nt Or the rc::t '--t r Ot ::ph r:-high r:d. :quir-d '

by th:

"inimum Ch: n:1: CP h :dicti:n 1 v;l 1:::d :t; en :ltern:t ::thed th: Oppr;;ri. D;ir;;;r'- r(:) .;ithin 72 '0ert, and Of ; nit ring cither r :ter: ----d '- OPEP^.SLE ct:te: wit"i" n

b pur:::nt t: " . thein;#I2::::rci:1 M ::ti r 5.0.2 itbi- ita:h.b: c:=i::ier 7 d:y: cr pr:pr: ;

d y: t ":: :ti:n:

f th: in p;r tility, and the pl n: :nd ::P m

^-

t z:r h .

,__...___,..m,,,,,-

~~~"='"'-~"'""~~'-~-

' ' ~ ~ ' -

C.

)( The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.

f CATAWBA - UNITS 1 & 2 3/4 3-65

TABLE 3.3-10 o

-4

> ACCIDENT HO:41TORING INSIRUHfNTATION -

2 10TAL HINIMUM

' N0. OF CHANNELS CilANNELS OPERABLE INSIRUMENT E.

--i 2 1 Contai;; cat "resser:

[

[(1.( -)1. Reactor Coolant Outlet Temperature - Il10f (Wide Range) 2 1 2 1 hm- h_ eactor Coolant Inlet Temperature - TCOLD ( ide Range)

1 2

3. M eactor Coolant Pressure - Wide Range 2 1

q. y Pressurizer Water Level 2/ steam generator 1/ steam generator Steam Line Pressure 2/ steam generator 1/ steam generator 4 'K Steam Generator Water Level - Narrcw Range m 2 1

7. K Refueling Water Storage Tank Water Level 2/'te generater 1/0t:2= generater

9. ^e? '!;ry fecie ter Flcu Rat w

8 _]t{ Reactor Coolant System Subcooling Margin Monitor T 1 2/Y2h 1/Y2 h

11. PORV Positicr. Indicatur*

- 2/V;he 1/Vahc

12. PCRV B?cck Va he Positica Indicats.**

o rescr-izer Saf ety Vahe Pesitica Indicater 1/Yahe 1/Y2 he 12.

C .ta:n :.t S =p U;tur Lcut! (Wide R;r.ge) 2 1 l'

N -

p .

1 TABLE 3.3-10 (Continued) 9 5! ACCIDENT HONITORING INSTRUMENTATION MINIMUM TOTAL

' NO. OF CHANNELS CHANNELS OPERABLE, E

INSTRUMENT

-e '

n Core Thermocouples 4/ core quadrant 2/ core quadrant

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t 1

TABLE 4.3-7 n

ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5

> CHANNEL CHANNEL d

. INSTRUMENT CHECK CALIBRATION c

Ceniciscat Pr=mc M R 1.

$ M 1.[ReactorCoolantOutletTemperature-TH0T (Wide Range) M R m eactor Coolant Inlet Temperature - TCOLD (Wide Range) M R

[ eactor Coolant Pressure - Wide Range M MJ R

R 4 Pressurizer Water Level team Line Pressure M R team Generator Water Level - Narrow Range M R

{hk

=

efueling Water Storage Tant Water Level M R

0. ..=i'icry Fecd: ter Flcu Rate M R

8. Reactor Coolant System Subcooling Margin Monitor M R

^0RV Pc;ition Indicator M R** k

, 11.

I

/f i'

12. PORV Sicck Vahc Pc;itica Indicator M R**

ff -

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.C

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>= e4 e4 c4 ee f J W t

CATAWBA - URITS 1 & 2 3/4 3-69 ' Amendment No. (Unit 1)

Amendment $. (Unit 2)

..a,m

-- 1YM

INSTRUMENTATION BASES REMOTE SHUTDOWN SYSTEM (Continued)

't t -

control and power circuits and transfer switches necessary to eliminate effects

-# } of the required fire and allow operation to achieve and maintain of instrumentation, control and

a. safe snutdown condition power circuits are independent of c

'- areas where a fire could damage systems normally used to shutdown the reactor.

This capability is consistent with General Design Criterion 3 and Appendix R

_g g to 10 CFR Part 50.

3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION 2-The OPERABILITY of the accident monitoring instrumentation en ures that G sufficient information is available on selected plant parameters to monitor 2 \ and assess these variables following an accident. Thi; capabilit3 i; c0n;i -

6 '1 ::nt = :n: rc :x:ncett;n: :QRegulatoryGuide1.97, Revision)f,"Instrumenta-E o tion for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions Our- .

J G. wingandFollowinganAccident","y1033andNUCEC0737,"Cirif(j;;ti;rOf?!-

e. ., ,, 0 3 ., ,, o._-.a..____., n u._x _w , a. .e n. .

gM;ron,

.. e V

" 4. 3/4.3.3.7 CHLORINE DETECTION SYSTEMS o

b ,*'The OPERABILITY of the Chlorine Detection Systems ensures that sufficient '

B:ap capability is available to promptly detect and initiate protective action in I g This capability is required to ,

q p the event of an accidental- chlorine release.5 protect control room personnell bo Regulatory Guide 1.95, Revision 1, "Protection of Nuclear Power Plant Control p 9 $ Room Operators Against an Accidental Chlorine Release," January 1977. j kw^

"h3/4.3.3.8 FIRE DETECTION INSTRUMENTATION h! .5 OPERABILITY of the detection instrumentation ensures that both adequate l

% } warning capability is available for prompt detection of fires and that Fire j

,g< Suppression Systems, that are actuated by fire detectors, will discharge '

4 extinguishing agents in a timely manner. Prompt detection and suppression of

] f fires will reduce the potential for damage to safety-related equipment an an integral element in the overall facility Fire Protection Program.

O Fire detectors that are used to actuate Fire Suppression Systems represent I a more critically important component of a plant's Fire Protection Program 3thandetectorsthatareinstalledso1Alyforearlyfirewarningandnotifica-

.ption. Consequently, the minimum numeer of OPERA 3LE fire detectors must be jgreater.

[ The loss of detection capability for Fire Suppression Systems, actuated by fire detectors, represents a significant degradation of fire protection for c

1:s

> CATAWBA - UNITS 1 & 2 B 3/4 3-5

l l

j

! INSTRUMENTATION 8 , l 1

k ACCIDENT MONITORING INSTRUMENTATION I LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With the number of OPERABLE accident monitoring instrumentation ,

channels less than the Required Number of Channels shown in l Table 3.3-10, restore the inoperable channel (s) to OPERABLE status '

within 7 days, or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l

b. With the number of OPERABLE accident monitoring instrumentation '

channels less than the Minimum Channels OPERABLE requirements of f Table 3.3-10, restore the inoperable channel (s) to OPERABLE status l within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at lesit-HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

( c. The provisions of Specification 3.0.4 are not applicable.

i SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.

McGUIRE - UNITS 1 and 2 3/4 3-55

~

Z. . %. c. d.co k d Te m et.m h e - Tco W . g. 3 1. t .' -

TABLE 3.3-10 W

c)

ACCIDENT MORITORING INSTRUMENTATION C

REQUIRED MINIMUM a

"' NO. OF CHANNELS

' INSTRUMENT CHANNELS OPERABLE C g j n____.__ i

, .z. i. . r.=._ ._.. m. ._ .z -_ ._ ._ _ i ..,..m m l d 1X Reactor Coolant Temperature - T HnT e=d Ttete (Wide Range) 2 1

- 3. Reactor Coolant Pressure - Wide Range 2 1

,, 4. Pressurizer Water Level 2 1 j R S. Steam Line Pressure 2/ steam generator 1/ steam generator j m 6. Steam Generator Water Level - Narrow Range 2/ steam generator 1/ steam generator l ~ J. Refueling Water Storage Tank Water Level 2 1 8 3 .^. uni!inry F:: dater Flew "st: 2/ 1 2: generater 1/ tec: generatcr 3 8. '"' Reactor Coolant System Subcooling Margin Monitor 2***

1 f

4

,..n, . . , , . . .

n.,_,,..m..,_.

.. . . . ~ . . . , . , .. .., .,. .._

1, u 1 /. . . ) .

l

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. n.

t

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. ...i. _ J t. w. ..__**

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...,.s,2.hu V.

L n

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_,_ ,i,,.._

.,.a..s T r__ __s , ,

2, j.......____.o...,.._ _ __ .. , _ . . _.m. n..._._.3,., m

_ , . us:. 2,_

! 9. In Core Thermocouples 4/ core quadrant 2/ core quadrant s e, . u.._.. :. . u.__.. u. . :. 3. .n..___ u _ o. ._. r. ._ _.~

. . . 3, . , , . . . . . . . . .

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, er

}

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.._. a

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c ro.,r

i s o. . . i .n . iV, ii, ic, is;

! 17 Centain :nt ^.t=::;2 r - "igh R ng: "criter 1 1 irme r,_ __

r,<s

( LD. JAG V. JAUf f l 18. (

z 4

Reacter

. . . u : a.. "_

scl Lcvel Instrucentaticr****

o. . ., _. 3. .

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., ., . . :. ... .a. u. ,_, . o., ~ . . ,

. _..,....'.i._.,a.

. v,. . , , . .

} nn __t

( A u. .,_, .. .. 7 7 . t. ., .,. L. . t. O. r. ...k.m. ..,,,,,..a

s. L,1. ._ ,_. mL ....1...,.

. . . . .. . .1.._,,_.J. y,, ., . ...: .

2.,., . _.L.,.

_ ._ ...,J. v.-

2., _--_._J..

3

***0nly-one channel per unit is required until the end of the first refuelingu_: . outage following 1/86 for each unit.fp

&. T **=,u_. _ .a : ,. ~ u _ . . _ . :, .<_ <__:__:__ _,

r. . _ i _ . ,___ u_:. ,

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CC DD ta= >'-

OM vv 1 q ^

w i

e *

%d4 TABLE 4.3-7 W

a ACCIDENT MONITORING INSTRURENTATTDN SURVEILLANCE REQUIREMENTS C

CHANNEL CHANNEL A INSTRUMENT CHECK CALIBRATION

. , , _ _ . .:____. n____..__

.. b V. 5 b tB 5 5 .. % . s b .5 LJ5 L

- o C

x

1K. Reactor Coolant Temperature - Tg0T 2 nd T ,. & .,. (Wide Range) M R w . . ,

- 3. Reactor Coolant Pressure - Wide Range M R

@l a

4. Pressurizer Water Level H R w S. Steam Line Pressure M R

6. Steam Generator Water Level - Narrow Range M R

7. Refueling Water Storage Tank Water Level M R n

_s

. 1,__.

., . ..., r,__1.

_.__ .r i. ._,.. . .n...,_ _

. o.

. o,

8. Reactor Coolant System Subcooling Margin Monitor M R w L in . __ ,_m __.__

i g au. nn ou. .n__

s v .i vJ .wavs. . su s su bv u u

ae o

i A

_ii w ... nn n.u. o. t. ._,s, t.

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a

.u. n,

$ -12. bafety '!ah: "c'viticr. Indicater ", "

j . )3.

Centair. cnt "ater Lc.cl ("idc Rangc) "

R j T. % In Core Thermocouples M R

ic ,,_:.

<__u._._...__

as. . . . u. s_ ._., . _u. :. 3.t. o. ._ ._.3,__ .u..L, i. s_.

uus . .. .o. ,n, .,

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)b. btOZ RC Of - f h,e

i. CChC 07. 507 k 4

g g v.. s v , _ ru.r _ ,,

A as 3 s. T , Lv,

,e Lv, en LsJ ag f , rur_in 11 1, ins ,

g _ gvr e n._s b La . La vu av, AA, AL, Asp 64 64

.7. COEI2 .^CCCt .MC C rf . $. CI.hC .C .^. IOI fror_ci, __ c,ts.

g7 g w ais v. .r .u p OO

.O. RCSCtO7 CCSC. 'n C "." C ,

. 7.3 t 7^.~.C . I sS t i 07. #

/

,.m o ___

1 u- u.

= n

...7 s. vi

_L.

u.r M..,m__

. . . v._ . O.._ _.3s M o =

g CC s

D. **

pa MM 3 (

ce z. %b GLA TemcAcc - Tc aMac 9 M 1

~

l

-E M

o L INSTRUMENTATION i -

3 2 ~

c c p o BASES L3 p, MOVABLE INCORE OETECTORS (Continueol -

Y* The OPERA 81LITY of tnis system is demonstrated by irradiating of the core.

)w y each detector used and determining the acceptability For the purpose of measuring Fq (Z) or F of its voltage curve.

N a full incore flux map is used.

3%

hg Quarter-core flux maps, as defined in WCAP-8648, June 1976, may recalibration of the Excore Neutron Flux Oetection System, and full incere be used in 4 flux maps or symmetric incore thimoles may be used for monitoring the QUADRANT j POWER TILT RATIO when one Power Range channel is inoperaole. 1 C

3/4.3.3.3 SEISMIC INSTRUMENTATION 4 ~

j The OPERA 8ILITY of the seismic instrumentatf on ensures that suf ficient 3,5a .-h capability is available to promptly determine the magnitvde of a seismic This caca- event i

and evaluate the response of those features important to safety.

yn J+

bility is required to permit comparison of the measured respo 2

27 ,[ pursuant to Appendix A of 10 CFR Part 100. The instrumentation is consistent Earth-with the recommendations of Regulatory Gv4de 1.12, "Instrumentation for (a s$ o g quakes," April 1974.

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that 8 suf ficient meteorological data are available for estimating potential radia-CE 3 tion cosas to the public as a result of routine or accidental elease of u ( radioactive materials to the atmosphere.

This capability is reauired to U.I evaluate the need for initiating protective measures to protect tne health ano MJ tsfety of tne public and is consistent with the recommendations of Regulatory n T Guice 1.23, "Cnsite Meteorological Programs," February 1972.

J't Y

>-- 3/4.3.3.S GENTE SHUT 00VN INSTRUMENTATION

,g

" The OPERABILITY of the remote shutdcwn instrumentation ensures tnat

=t$

V y sufficient capability is available to permit snutdown and maintenanceThis of *0T lN STANOBY of the facility from locations outside of the control rocm.

~

0 _.I, capability is re:uired in the event control room habitability is lost anc. is d consistent with General Casign Criterion 19 of 10 CFR 50.

3 cn g n j V 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instet. men tion ensures tnat

) sufficient information is available on selected plant pa ameters to monitor :r t '-

c p& and assess these variables following an accident.

t;nt d th in; r;;;x;nc ti;n; ;- Regulatory Guide 1.97, "Instrumentation

i;k;;;;;ity':

Conditions Duringf ano or L

'N lants to Assess Plant"q"I~2 L;;;;"; L; r';d -

i

' 4c.$) j( Light-Water-Cooled Nuclear PowerFollowing an Accidentg T :t Nr;; Sten; t,;;rt ;nd h;rt-!;,: 5 ;; .~ -00t'0 ;

" -h ;;;;;r '073 rd M

7 '

cal.Ewirorts i f $' McGUIRE - UNITS 1 and 2 9 3/4 3-3

e

-,, N (

SSTRt;XENTATION

@ G L- {'fh BASES x

Instru=entation System (RVLIS) . is des t to =onitor the The Reactor Vessel lav vessel, or the void content under reed circulation water level in the reacco The R' S was installed as a conditions, during postulate accident conditions. ) as required by part of the Inadequate Core Coo ng Instrumentation (

NU RIC-0737.

The system consists o three level ch . als are thewhich upper indicate range (64on the

- 120%),

The channe Inadequate Core Cooling Monitor. d (D/P) range (0 - 120%). The upper the lover range (0 - 70%), and the dyna evel measurements over a specific range and lower range channels are actu actor lant pumps running. These channels height of the reactor vessel with no pumps operating. The dynamic indicate "invalid" with one or m utialreactor cool pressure acto the reactor core when the head channel indicates a dif erating reactor coolant pumps are f and indicates "inv d" with no pumps running. i are required to be operable by Technic Specifications are l

The two channels th the lower range d the dynamic head range. The upper range is oc required Cooling because it d not secte to monitor or mitigate an Inadequate Co venting l Incident. ihe upper range channel vould be used to assist opera tors (

nonce- nsible gases from the upper head of the thereactor core isvessel; a level covered, thus an,. dication or ne upper range channel vouAd indicate that ;

.nadequate core cooling event;has been terminated. !

l l

l

(

8 3/4 3-3a

a l ATTACIIMENT II DISCUSSION AND ANALYSIS OF NO SIGNIFICANT IIAZARDS CONSIDERATIONS i

)

1 l

l l

c 1

. l DISCUSSION AND ANALYSIS OF NO SIGNIFICAMP HAZARDS CONSIDERATION The proposed amendment to Technical Specification 3.3.3.6 and Tables 4.3-7 and 3.3-10, Accident Monitoring Instrumentation, would revise the Technical Specifications to reflect the analysis performed in accordance with Regulatory Guide 1.97, Revision 2.

On December 17, 1982, Generic Letter No. 82-33 was issued by D. G. Eisenhut, Director of the Division of Licensing, Nuclear Reactor Regulation, to all licensees of operating reactors, applicants for operating licenses and holders of construction permits. This letter included additional clarification regarding Regulatory Guide 1.97, Revision 2 relating to the requirements for emergency response capability. These requirements have been published as Supplement No. 1 to NUREG-0737, "'1Til Action Plan Requirements".

Duke Power provided responses to the Regulatory Guide 1.97 portion of the generic letter for the Catawba Nuclear Station, Units 1 and 2, on September 26, 1983.

Additional information was submitted on October 22, 1985 and March 25, 1986.

Responses for the McGuire Nuclear Station, Units 1 and 2, were provided on Mr.rch 24, 1984, August 30, 1985, April 14, 1986, May 22, 1987 and August 17, 1987.

The NRC Staff responded to the Catawba Study in Supplements 4 and 5 to the Catawba SER (NUREG-0954). Response to the McGuire submittals was provided in a letter dated February 12, 1986, which transmitted an Interim Technical Report.

Although there is still one outstanding issue open on Catawba's Regulatory Guide 1.97 review (i.e., qualified accumulator discharge instrumentation) the proposed Technical Specification changes are appropriate. The accumulator tank level or pressure are not referenced in any emergency procedure covering design basis events which may cause a harsh environment. No operator actions in these procedures are based on accumulator indications. Therefore, this instrumentation would not meet the requirements for inclusion in the Accident Monitoring Instrumentation tables.

A separate issue is still outstanding on the McGuire review dealing with the need for qualified wide range steam generator level instrumentation. For the reasons advanced in the August 17, 1987 letter from Duke to the NRC, the wide range instrumentation has not been proposed to be added to the McGuire Technical Specification tables. The narrow range instrumentation is currently included in the tables and will be retained. It is this instrumentation that is relied upon i in the McGuire emergency procedures for accident mitigation with the one I exception as noted in the August 17, 1987 letter.

Regulatory Guide 1.97, Revision 2 divides the post-accident monitoring instruments into five variables (A, B, C, O and E) providing a graded approach to requirements depending on the importance to safety of the measurement of a specific variable. Type A Variables are those variables to be monitored that provide the primary information required to permit the control room operator to take specific manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis accident events. Primary information is information

v DISCUSSION AND ANAIMSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION (Continued) that is essential for the direct accomplishment of the specified safety functions; it does not include those variables that are associated with contingency actions that may also be identified in written procedures. Types B, C, D, and E are variables for following the course of an accident and are to be used (1) to determine if the plant is responding to the safety measures in operation and (2) to inform the operator of the necessity for unplanned actions to mitigate the consequences of an accident. The five classifications are not mutually exclusive in that a given variable (or instrument) may be applicable to one or more types, as well as for normal power plant operation or for automatically initiated safety actions. A variable included as Type 8, C, D, or E does not preclude that variable from also being included as Type A. Where such multiple use occurs, it is essential that instrumentation be capable of meeting the more stringent requirements.

On February 6,1987 the NRC published its Interim Policy Statement on Technical Specification Improvements for Nuclear Power Reactors (Federal Register Notice 52 FR 3788). Included in this Interim Policy Statement were three Technical Specification split criteria to be used to evaluate the need to retain requirements in the Technical Specifications. Application of the criteria to the Accident Monitoring Instrumentation Specification by each of the Owner's Groups I t

has shown that only Criteria 3 would be applicabic. Criteria 3 directs that an item to be retained in the Technical Specifications would be:

A structure, system, or c_mponent that is part of the primary success path and which functions or actuates to mitigate a Design Basis Accident or Transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

l The Type A Variables proposed to be included in the Accident Monitoring l Instrumentation Tables would be the only instrumentation captured by the j application of the split criteria. Type B, C, D and E Variables would not meet l any of the split criteria and therefore should not be required to be in the l Technical Specifications. I Based on the above discussion and the guidance contained in Regulatory Guide 1.97, Revision 2 it is recommended that the instrumentation identified as being Type B, C, D or E be relocated out of the post-accident monitoring instrumentation specification. Technical Specification 3.3.3.6 and Tables 3.3-10 and 4.3-7 should be revised to include only Type A Variables consistent with the recommendations contained in Regulatory Guide 1.97, Revision 2 and the approprial.e correspondence between Duke and the NRC Staf f.

The appropriate Bases section is to be revised to reference Regulatory Guide 1.97, Revision 2 and will specify

hat the Technical Specifications on post-accident monitoring instrumentation address only Type A Variables as defined in the Regulatory Guide.

The requirements for relocated instruments will be placed in the FSAR. The applicable LLaiting Cond.itions for Operation, Action Statements and Surveillance Requirements will also be relocated to the PSAR. This will ensure that there will be adequate controls maintained on the relocated instrumentation. Please note that a correction is being made to item 9. on Catawba's Table 3.3-10 and

4 DISCUSSION AND ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION (Continued) item 8. on McGuire's Table 3.3-10 concerning the Total Number of Channels for Auxiliary Feedwater Flow Rate. This change is cons 4 stent with the Regulatory Guide 1.97 review.

10 CFR 50.92 (c) states that "a proposed amendment. . . involves no significant hazards considerations, if operation of the facility in accordance with the proposed amendment would 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 margin of safety".

This ame.odsent request would not significantly increase the probability or consequences of an accident previously evaluated.

In the discussion section of the NRC's Interim Policy Statement for Technical Specification Improvements it was stated that "the Commission recognizes the advantages of improved Technical Specifications". Mainly because "it will result in Technical Specifications that focus licensee's and the plant operator's attention on those plant conditions most important to safety...". Thu proposed changes to the Accident Monitoring Instrumentation Tables would retain those instruments which would meet at least one of the three proposed Technical Specification split criteria. It is these instruments (Type A Variables) which are most important to safety. The Type A variables cre those instruments l identified via the Regulatory Guide 1.97, revision 2 review and are those instruments identified which are to be retained in the Technical Specifications.

Instrumentation to be deleted from the Accident Monitoring Instrumentation tables will be relocated into the FSARs for McGuire and Catawba. Adequate control via the requirements of 10 CFR 50.59 will ensure that this instrumentation will be maintained operable.

The proposed changes will not create the possibility of a new or different kind of accident since the requested changes only apply to post-accident instrumentation.

No hardware changes will be implemented and the station will not be operated in any different type of configuration than currently allowed. Any modifications to instrumentation or their applicable procedures which would no longer be contained in the Accident Monitoring Instrumentation Tables would be reviewed in accordance with the requirements of 10 CFR 50.59. This review will ensure that any proposed changes to these instruments or the applicable procedures will not involve an unreviewed safety question.

i The proposed amendment will not involve a significant reduction in a margin of safety. With this amendment several items will be removed from the affected Technical Specification Tables and relocated to the FSAR. The instrumentation to be relocated has not been identified as Type A Variables per the Regulatory Guide 1.97 review. In accordance with the intent and guidance of the NRC's Interim Policy Statement it is not necessary for these items to be retained in the Technical Specifications for Post-Accident Monitoring Instrumentation. The

4 DISCUSSION AND ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION (Continued) instrumentation to be retained is identified as Type A Variables. It is this instrumentation that is deemed to be of immediate importance for post-accident monitoring. This instrumentation meets all the Regulatory Guide 1.97 requirements set forth for Type A Variable instrumentation with exceptions as noted in our referenced responses.

The outcome of the proposed change would not significantly decrease the margin of safety since the Technical Specifications would now contain only those instruments identified as Type A Variables. More emphasis will be placed on maintaining the operability of these instruments. Instrumentation to be deleted from the Technical Specifications will still be maintained in accordance with the existing applicable procedures. Any changes to the procedures or the instrumentation relocated to the FSAR would require an evaluation in accordance with the requirements contained in 10 CFR 50.59. This review would ensure that any changes would not involve an unreviewed safety question. Additionally, a multidisciplinary review by the Nuclear Safety Review Board per Technical Specification 6.5.2.8c. is required of all 50.59 changes. These controls are adequate for assuring these instruments are maintained operable.

Based upon the above discussion, it is concluded that this amendment does not involve significant hazards considerations.

l l

)

o l

ATTACHMENT III PROPOSED ADDITIONS TO FSAR CHAPTER 16

Ib)3 INSfRUMENTATION

,7,j, ACCIDENT MONITORING INSTRUMENTATION L:":T:t:0 00t:0:T:0t: r0n Or:nAT:ct: COM/TMENT IG.7-l

.2.2.0 The accident monitoring instrumentation channels shown in Table 3.2 10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

p 6tlAL ACTION: g,j

a. With the umber of OPERABLE accident monitoring instrumentation channelsql ess than the Total Number of Channels shown in Table-2. 10, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUT 00WN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. With the number of OPERABLE accident monitoring instrumentation channels except the unit vent-high-high range area monitor, the steam relief valve exhaust radiation monitor, the containment atmosphere-high range radiation monitor, and the reactor coolant radiation level less than the Minimum Channels OPERABLE requirements

! \b.7'g ~ of Taole12.0-10, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With the number of OPERABLE Channels for the unit vent-high-high range area molitor, or the steam relief valve exhaust radiation monitor, or the containment atmosphere-high range radiation monitor, or the reactor coolant radiation level less than requirea by the Minimum Channels OPERABLE requirements, initiate an alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and either restore the inoperable channel (s) to OPERABLE status within 7 days or prepare and submit a Special Report to the Commission 7 pursuant to1 Specification 6.9.2 within 14 days that provides actions l h taken, cause of the inoperability, and the plans and schedule for j dpd restoring the channels to CPERABLE status.

m. Ti r. . . . . . ... o f Sp;;i f k Ao 2. 2. 2 L ; .,;t ;;pii 21;.

~T1!sTid4 UnW :LLA.NC: RE0VIREMENTS 2.2.:.: Each accident monitoring instrumentation channel snail be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.0-1

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IABLE-3.3 la (Continued)

$l 5,2 ACCIDENT MONITORING INSTRUMENTATION O

"

TOTAL HINIMUM NO. OF CilANNELS CilANNELS OPERABLE

! E INSTRUMENI M 4/cerc c,u;dront 2/cera r,uad.ar,t X Ir. Carc Thcrs ccup!c:.

]

Unit Vent - liigh-liigh Range Area Monitor (EMF-54) N.A. 1

f. )(.

Steam Relief Valve Exhaust Radiation Monitor (IEMF-26, 27, 28 or 29 N.A. I

8. M.

and 2 EMF-10, 11, 12 or 13)

9. K Containment Area - liigh Range Radiation Monitor (EMF-53 A or B) N.A. I 2 1

10. M(, Reactor Vessel Water Level N.A. I

u. M. Reactor Coolant Radiation Level (EMF-48)

N TABLE NOTATIONS

Not applicable if the associated block valve is in the closed position.

- Not applicable if the associated block valve is in the closed position and power is removed.

I f,.7-2.

lABLE m WSTIM o

P. ACCIDENT MONITORING INSTRUMENIAll0N SUL'E'LL;.MCC REQUIREMENIS

- o

~

1

' ' CHANNEL CHA.WEL CHECK CALIBRATION INSTRUMENT c

35 1. Containment Pressure n R

-4 L1 "

,, 2. Reacter Caetant Out!:t ! :perature - T HOT I"id" R""S") E s - "

,2 3. Reacter C !;nt Inlet T =perature - T COLD

"=S")

" a

' Re2cte: Cee!2nt retter: - Y!de R:n; o rescer5:::' 2 S. "2ter L : !

R

5. Ste r !ine Precsure

! " R l St Stec: Cener2ter "2ter L:: ! "2rreu R:ng:

o J

l s,

, .o. o_..,....i.:.....

.3 o._

c,.__,._

....3 .

s. . _.

r. ., .a. _ u--..._.._i.

... u.

o, i yrb (D

M R 2.)( Auxiliary feedwater Flow Rate

10. Reacter Cuct;nt Syst = Ex' ; : !:ng "crgi ".: niter M R**

3, K. PORV Position Indicator M R**

.i . 'l.11. PORV Block Valve Position Indicator

.l .i hr M R

{ [j

< ,n

[ 6 )d. Pressurizer Safety Valve Position Indicator j! P, lo, M. Containment Sump Water Level (Wide Range) M R ifif .

lO kO s%s%

4 I a5

-~-

n'* 4*

IJDJ ssr,s i

~

41 yESTidt 1ABLE M (Continuad)

!k ACCIDENT MONITORING INSTRUMENI ATION S'"".'EILL!.MCEJREQUIREMENTS F

p CilANNEL CilANNEL

!! Cl!ECK CALIBRATION hi> r' 1. sJ)

M

!! 45. I.-

s e ~;w-;.ccoupics M M k

- Q)(f, Unit Vent - liigh-liigh Range Area Monitor (EMF-54) s .

, g, M . Steam Relief Va he Exhaust Radiation Monitor (1 EM)-26, 27, M R 28 and 29 and 2 EMF-10, 11, 12 and 13)

Cantyinment Area - liigh Range Radiation Mon! tor 9, y(.

(EMF-53 AAB)

M R*,** [

M R y, % Reactor Vessel hater Level M R l' g, DCL Reactor Coolant Radia!. ion Level (EMF-48)

( 2 O

CllANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for range decades above '.0R/h and a one point calibration check of the detector below 10R/h with an installed or portable gamma source.

i i : i

- This surveillance need not be performed until prior to entering 110T STANDBY tollowing the Unit 1 first 4

i ;

refueling. (This applies to Unit 1 only.)

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4,9 INSTRUMENTATION

,g ACCIDENT HONITORING INSTRUMENTATION I

.........mm.....,

m......_

em. mm.

_........_..._....mi, . . _

DOM /'f/7d 6N 7

-0.0.0.0 The accident monitoring instrumentation channels shown in Table 17-/

0.0 10 shall be OPERABLE.

APPi!CABILITY: MODES 1, 2, and 3.

,4 ACTION:

3

a. Wich the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in g(p.9'g ~ ~ Table}0.0 10, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With the number of OPERABLE accident monitoring instrumentation channels less than the Minimem Channels OPERABLE requirements of 4 4L M bf% 0.0-10, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at leaTt HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. The pr;vi;ien; cf Opc;if ::.;ica 0.0.4 are n;t applicable.

TESTING OU"',':'LLANCC REQUIREMENTS 4.0.0.0 Each accident monitoring it.strurnentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CMECK Lid CHANNEL CALI3 RATION operations at the frequencies shown in Tabis '.0-7.

A 16.? m

tm 16.7 -l

---HeGU I "C UN MS 1 end 0 0/4 0 00-

. s (L 7- I ,

TABLE 3.3 10

r r ,

ACCIDENT MO N TRUMENTATION o

e REQUIRED MINIMUM r' NO. OF CHANNELS CHANNELS OPERABLE INSTRUMENT c 2 1

?; 1. Containment Pressure "cec ^er C;; lent ! ,,cr;ture - T,iQy_end-ICOLD Nide hagc) 2 1 d 2. , , _

_ u o.--_ . , - . . , , ,

, o___.__ ,.__i__..._,,_.._m_ _ __

g .. _ . . . .

2 :

+ Pres',tri:cr Wicr Lcyc!

2/stc;; gencr;ter 1/:,tc = g..crat;r Sic;; Line "ressure L S.

S ic = Cc ac ri.te r W ic t L ,.cl " a r e.; agc 2/stc = gencr;ter 1/stc = gcacrat;r S. !

7. "cf.,elir.g W '- p tereg T;..k W icr tcvc! A 1/ steam generator 2.K Auxiliary F ate:r Flow Rat: Q

k*

steam

generator

React:r C;;. .-b fy',tc= 5 ':;;!ing H;,gi,.".; nit;r 2 I 1/ valve f

2/ valve l 3 PORV Position Indicator

1/ valve 1/ valve

4 PORV Block Valve Positior. Indicator ** 2/ valve 1/ valve

5. )U Containment Safety Valve Position Indicator Water Level (Wide Range) 2 1

<, (. .R '/cccc quadraat 2/cccc quedcent y l'. In C;rc it.c. .;;;;;;lc; 1 1

7. $ Unit Vent - High Range Noble Gas Monitor l t,

(High-High Range - EMF-36) 1/ steam line

~ o o Steam Relief - High Range Monitor 1/ steam line

8. K (Unit 1 - EMF-24, 25, 26, 27) i (Unit 2 - EMF-10, 11, 12, 13) 1 Containment Atmosphere - High Range Monitor 1

'). %

i 10,% Reactor Vessel Level Instrumentation ****

(EMF-Sla or 51b) .[9 l a. Range g g p) 2 1 j 2 1 ,

b.

4 I h. ..;cr= Hange l Nw W i .i a

"Not applicable if the associated block valve is in the closed position.

l i I 1

ll l

- Not applicable if the associated block valve is in the closed position and power is removed.

f;f ***0aly e..; che..nc! f,cr unit is required unt!! the end of the first refec? f ag ;;t;;c f;?!=ing 1/06 for cach sait.

- - - Not applicable until the beginning of Cycle 4 for Unit I and Cycle 3 for Unit 2.

l . . ~,

4 4 >1 I !$$,

i s im 4 P4 >

4 % #

3 h

1

b S

II . f -2. 7g51rdf TABLE +-3 F ACCIDENT MONITORING Ii4STRUMENTATION SUR'!CILLA%CC (REQUIREME n p h CHANNEL CHANNEL ff INSTRUMENT CHECK CALIBRATION

1. Containment Pressure M R SE

2. Rcactor Ceolar.t Teryerattri e T g and T I **N E

] COLD

~ 2. Rcect:; C;;?;c. P.c;;urc Mi& Rac.g "

9' . Pic;;uri;cr L';ter Lcvc? M R i-r, S. Sic a Lir.c Prc;;urc M R C. Sica; Ocr. crater Water Levc! Marre- Range X R

7. ScfteeFing-Watcr Stor:g Taak Water Levci X R Z.%. Auxiliary feedwater Flow Rate M R

0. Reactsr Ccciant-Syste Subcaeling Margia Maniter "

R t

3.}8, PORV Position Indicator M R J>

q , q, % PORV Block Valve Position Indicator M R 5; f. Y Safety Valve Position Indicator M R

(, . M. Containment Water Level (Wide Range) M R

-E - -ht-Ecre The. cc;gic; M R

~}. E Unit Vent - High Range Noble Gas Monitor M R (High-High Range - EMF-36)

J i r g- 6. M. Steam Relief - High Range Monitor M R

! f (Unit 1 - EMF-24, 25, 25, 27) h; l -

(Unit 2 - EMF-10, 11, 12, 13) o o gg 9. V'. Containment AtmospP - High Range Monitor M R

.,., (EMF-Sla or $1b)

' un "-

10 M. Reactor Vessel Level Inst umentation )

$M a. hrRange _

g qpfj) M R $

b. -Mew Range M R l 39: r f

-ww /

.o- . -

, fD 4 P u

i l

. _ - _ . . _ - _ _ _ _ - _ - _ - - _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ - - - _ - - - _ _ - _ _ _ _ _

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