ML20105C389

Forwards Comments & Recommendations for Changes to Tech Specs Resulting from Branch Review.W/Exception of Items Identified in Encl,Tech Specs Acceptable.Meeting W/Licensee to Obtain Info Re Recommendations Necessary

ML20105C389
Person / Time
Site:	Grand Gulf
Issue date:	10/31/1983
From:	Rosa R Office of Nuclear Reactor Regulation
To:	Thomas C Office of Nuclear Reactor Regulation
Shared Package
ML19303B912	List: AECM-83-015, Requests That NRC Endorse Util Interpretation of Tech Spec 3/4.3.6 Re Source Range Monitor Interlock Operability ML20105C382 ML20105C389 ML20105C424 ML20105C621 ML20105C997 ML20105D004
References
NUDOCS 8311100408
Download: ML20105C389 (3)

Text

{{#Wiki_filter:= &# t-I b4 Msc +, - - ~ h .x .. y. MA,) C,4-O3 LI All,=~ 5 . ---.g f [..f. jf 8e, UNITIC STAf t3 I P* NUCLEAR REGULA: CRY CCMMISr.!CN .h s %2W j W A3MNGTON. C. C. 2C$$3 \\.',l'M GCI 31192!3 MEMORANDUM FOR: -;, .2_ " - " w......,,........, FRCM: Faust Rosa, Chief, Instrumentation & Centrol Systems Branch Division of Systems Intagration a

SUBJECT:

GRAND GULF - UNIT 1; ICSS REVIEW OF TECHNICAL SPECIFICATIONS P1 ant Name: Grand Gulf-Unit 1 Occket No.: 50-416 ~ ' Licensing Status: OL. Project Managea: Cean Housten Review 3 ranch: ICSB ~ Review Status: Technical Scecifica:icn Review Ccmpleted As recuestad by your memorandum dated Oct:ber 4,1985, the Instrumentation anc Cen:rol Systems Branch (ICS3) has reviewed the Grand Gul f-Unit 1 Tech-nical Specifications witnin ICS3's scope. As Enclosure 1, I am providing our c:m=ents and recommendations for changes resulting frem cur review. As, I am providing a' list oi' the T' chnical ' Specifications re'vieke'd ~ e by the ICS3. Please not. that radiation, chlorine, scismic, metarological, and fire protection instrtmentatien are not within the ICSS scoce. With' the exceptien of the items identified in Enclosure 1, the ICSB has deter-mined that the Grand Gulf-Unit 1 Technical Specificaticns are acceptable. A mee:ing with the licensae may be desirable to obtain the additicnal in-formation necessary to implemen: cur reccem,encation. .s Pleas' centact us if we can be of further as'sistance. e e CT e-

1. ^

Faust Rosa, Chief Inst.-:mentatien 1 C,:nt. ol Systems Scanch Civision of Systams In:agrati n F .:. closures: k[y A5 5 2~8C b c g (( cc: R. Mattson g R. Houston i F. wiraglia 0. icf fman

3. Houst0n Ocntact:

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c-m - w 6. e.,. y,t,, 3 ,i- . s. . strument uncertainty allotted for the trip unit drift. The numerical difference between the trip setpoints and allowable values for Grand Gulf include both trip unit drift and sensor drift... This extra drift s allowance could permit continued operation with instrument channels that would not actuate safety systems to terminate transie'ntior'5itigate accidents within the bou'nds specified in the FSAR analyses. The're fore,

• ' ~~

t the Grand Gulf-unit 1 Technical Specification's trip setpoints and' allow "--- able values should be revised to include only the drif t associated with ~ -- s .. - that portion "of. the. ins,trument channel. tested at 31 day intgrvaJ s41.e.7. '.-.P t-tri'p ' unit). Additional changes to the Grand Gulf-Unit 1 Technical Spe' i '.- 1-c fications'ma' be required following our review of the' licensee's metho'd d2 y ~ .t' ology' position statement. ' ~ t. .._...-~,,..c,.- 5. By letter dated October 11, 1983 from J. McGaughy (MP&L) to H. Denton 1"*.' * (NRC) the'11cansee proposed changes to th s Grand Gulf-Unit 1 Technical' * *' *:~ :

• * - t:
• : Specifications that address the RCIC ac.uation instrumentation. We haVe --.~ ~ ~
• t* " ' reviewed the* proposed changes and found them acceptable. A discussion on'. - L

h.'

• the prooosed changes ts contained in' the ICS3 inpu' to Supplement lio.' 5 of..

e ~ C.*** : the SER." The Grand Gulf-Unit 1 Technical Specifications should be revised:" 7 4

• 6't**

accordingly. e I -- I-n a t' !"6.* By letter' dated' October 14, 1983 from L. Dal e (MP&L) to H'.' Denton the'. - * * * * * ' licensee ' committed to propose revisions to the Grand Gulf-Unit 1 Tech

• " e.

+: nica1 *Seecificai; tons. The proposed changes will require more frequent '. t*?

• * * ~~~

calibrations of ecmponents in the containment isolation actuation instru '. i f mentation. We have reviewed One procesal and found it acceptable. A discussion on the proposal 1s contained in the ICS3 inout to Suoplement tio. 5 of the SER. The Grand Gulf-Unit 1 Technical Specifications snouId ce revisec accordingly. ..n "t .me,-+ w g he m g*-

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AECM-84/0093 j Page 11 DEFINITIONS FOR " CHANNELS", " TRIP SYSTEMS", AND " TRIP FUNCTIONS" FOR REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRL' MENTATION TABLE 3.3.5-1 Trip Unit Parameter Logie I ~ B21-LS-N6928 RPV Level - Lvl 2 r i l iB21-LS-N692F RPVLevel-Lvl2*l ~ One out k--- g of two I B21-LS-N692A RPV Level - Lvl 2 twice -Either RCIC ! B21-LS-N692E RPV Level - Lvl 2 One l Initiation l E51-HS-M625 Manual Initiation g B21-LS-N693A RPVLevelHigh-Lvl8] Close .B21-LS-N693B. RPV Level High.Lvl 8 s Bothe E51-F045-

• ] E51-LIS?-N635A Condens* ate"Stg Tank Level Lo~*

g , E51-LIS-N635E Condensate Seg Tank Level Lo - Any Switch I E51-LIS-N636A Suppression Pool Wtr Lvl Hi One g Pump I E51-LIS-N636E Suppression Pool Utr Lvl Hi y Suction to I Suppres-g sfon Pool g TRIP l FUNCTION { TRIPSYSTEM]

• One Channel (Typical of 11 shown on this page) i S

p e O g e e 13sp25 - -u +.

m_..,,- m.-_ s TECHNICAL SPECIFICATION PROBLEM SHEET F Item Number: 168 Priority: f/A / Identified By Date Responsible Supervisor Tech Spec

Reference:

3.6.3.1 i Problem

Title:

Suppression Pool Temo Recuire in OP condition 3 1. Problem Description (T'ech Spec, FSAR,' SER, GE Design, 0%er): The Spec is confusing because it doesn't contain any action statements for op condition 3, although the operator is instructed to go co Cold shutdownf. ' *1 - 2'. , Safety S1gn3.ficance: - Operating instructions are confusing. 3. Anticipated Resolution: Investigate to see if statement need rewording or if CCO should be appli-1 cable in op condition 3 as well as 1 and 2. ( Cou let use Sb fe& Y WW NYW'" s 4a.N(Asitv> be. gee 4. NRC Response to Item (NRR/IE): NRC Notified: / Individual Notified Date Time

5. Tisp'ositten:.*,

f. e' a Items Closed: (How) / Date Time cc: J. E. Cross R. F. Rogers e 1 , J - 3..l ) a

~ g... I TECHNICAL SPECIFICATION PROELEM SHEET Item Number: 185 Priority:,//// / Identified By Date Responsible Supervisor Tech Spec

Reference:

T.S.3.11.2.7 & Surveillance 4.11.2.7.1 Problem

Title:

Change " Hot Standby" to " Cold Shutdown" 1. Problem Description (Tech Spec, FSAR, SER, GE Design, Other):

1) Spec directs operation to go to hot standby, but should say cold shutdown.

2) Sampling is required prior to entering op condition 2, when the system is not in service, which is an unnecessary monitoring requirement.

~' . ~.~. 2. Safety

• Significance:' None: Investigation Required.

7 ' 3. Anticipated Resolution: 1) Change to cold shutdown. 2) Add to Surveillance 4.11.2.7.1 an exception to 4.0.4 to not samp..e till after entering op condition 2. S ec fes/69 S z% Hmu Y. Cou ld u.s e 12 c A f ( 4. NRC Response t'o Item (NRR/IE): NRC Notified: / Individual Notified Date Time 5. Disposition: ?.. Items Closed: (How) / Date Time l' ec: J. E. Cross R. F. Rogers I 74_g,e,m9,g w ar - gW, Y ] _} y y-b#

w-...-......a~ s.I t J 1; ).* TECHNICAL SPECIFICATION PROBLEM SHEET '( Item Number: 198 Priority: lA / Identified By Date Responsible Supervisor Tech Spec

Reference:

Table 3.3.7.1-1 items 6.7,8,9 Problem

Title:

Radiation Monitor 1. Problem Description (Tech Spec, FSAR, SER, GE Design, Other): Min channels required operable for items 6, 7, 8, 9 not the same even though logics are the same. 2. Safery Significance: Investigation required if 4 minimum channels are required ~and since presently v2 6nly require 3 channels operable, sie could be operating unconcervatively in relation to FSAR analysis. ~ 3. Anticipated Resolution: Investig/03/bk 6 6 femte fate; gropose Tech Spec change if req Cou ld &t..s g TecA $fde ( 4. NRC Response to Item (NRR/IE): NRC Notified: / Individual Notified Date Time 5. Disposition: ~ Items Closed: (Hov) / Date Time 1 cc: J. E. Cross R. F. Rogers ( , y., _ =.

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.I.' b 4 &Ac k m c.mi l It.en G*L ) Trip Unie Parameter Logic ] Either-C71-PIS-N650A Drywell Pressure-High I B21-LS-N682A RPV Level 2 l' l TRIP FUNCTION a ,,H21-BS-M630A Manual Initiation * -Both I - 'i L Note 1 [ C71-PIS-N650D Drywell Pressure-High y Eitherd g B21-LS-U682D RPV Level 2 521-RS-M630D Manual Initiation I g D17-RITS-K617A Fuel Handling Area Vent. I g Exh. Rad. Hi-Hi Both I I- ' DiT-RITS-K617DFuel Handling Area Vent. -Either-{ TRIP FUNCTION Exh. Rad. Hi-Hi d 5 I ]'D1 -RITS K618A ' Fuel Handling Area Pool " Sweep' l Note Ji Exh. Hi-Hi -Both-( l DiF-RITS-K61SD Fuel Handling Area Pool Sweep I +,2r n-Q l Exh. Hi-Hi j l TRIP SYSTDi L I Notes:

1) Closes Containment Outboard Dampers, Dryvell Ventilation Inboard Dampers.

Starts Standby Gas Treatment "A", closes Auxiliary Building Tual Handling Area Inboard Dampers, closes Auxiliary Building Ventilation Systen Inboard Daapers, closes Containment Ventilation System Inboard Dampers, closes Control Room Ventilation System Outboard Dampers, Starts Control Room Emergency Filtration "A".

2) Starts Scandby Gas Treatment "A", close Auxiliary Building Fuel Handling Area Venti 4 tion Inboard Dampers, closes Auxiliary Building Ventilation Syttes Inboard Dampers, closes'Containmeine Vent (lation System (Auxiliary *

• Building Inboard Dampers)

~ One Channel (typical of 10 shown on this page) e 46 ~~'y- ', p r p._ta_ / ;:- - - *' M ~ ~ - ^ ~ ~ ~ ~

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- Both-- l-TRIP FUNCTION lL 'J I Note 3 C71-PIS-N650C Drywell' Pressure-High ] Either l ( B21-LS-N682C RPV Level 2 B21-ES-M630C Manual Initiation I D17-RITS-K6173 Fuel Handling Area Vett. 9 i Exh. Rad. Hi-Hi Bothy ( D17-RITS-K617C Fuel Handling Area Vanc. I ~ g Exh. Rad. Hi-Hi --Either L-TRIP FUNCTION. D17-RITS.-K618B, Fuel Handling Area Peel.Sweepl'. I Note 4 gl Exh. Hi-Hi - Both ( t ( D17-RITS-K518C Fuel Handling Area Pool Sweep - l 3 Exh. Hi-Hi J i TRIP SYSTEM t. l Notes: 3) Closes Containment Inboard Dampers, Drywell Ventilation Outboard Dampers, Starts Standby Cas Treat =ent "B", closes Auxiliary Building Fuel Handling ~ Area Outboard Dampers, closes Auxiliary Building Ventilation System Outboard Dampers, closes Containment Ventilation System Outboard Dampers, closes Control Room Ventilation System Inboard Dampers, Start Control Peom Emergency Filtration "B".

4) Starts Standby Cas Treatment "B", Close Auxiliary Building Fuel Handling' Area Ventilation System Outboard Dampers, closes Auxiliary Building

~ Ventilation System Outboard Dampers, closes Containment Ventilation System (Auxiliary Building Outboard Dampers.)..

1. 'One Channel (Typical of 10 shown on this page)

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e g '. TABLE 3.3.7.1-1(C:ntinkd) PA01AT10N HONITORING_ INSTRUMENTATION -(.* o ALARH/ TRIP MEASUREMENT HINIMIAI CHANNELS APPLICABLE !{I c, p-INSTRUMENTATION DP.RABLE CONDITIONS SEiPOINT __ RANGE ACTION T E

10. Area Monitors q

a. Fuel Handling Area Monitors s ~2 3

1) - New Fuel 1

(e) 52.5 mR/hr/NA 10 to 10 mR/hr 72 I Storage Vault i d t l -2 3 1 2) Spent Fuel 1 (f) [ 52.5 mR/hr/NA 10 to 10 mR/hr 72 Storage Pool 1 -2 3 3) Dryer Storage ' Area (g) 52.5 mR/hr/NA 10 to 10 mR/hr -72 -2 3 0 1:' b. Control Room 1 At all times <0.5 mR/hr/NA 10 to 10 mR/hr 72 ~ Radiation Monitor T u, i With RHR heat exchangers fu operation. a When irradiated fuel is balng handled in the primary or secondary containment.- f Initial setpoint. Final Setp::!ni to be determined during startup test program. Any required change to i' this setpoint shall be submitted to Commission within 90 days af ter test completion. I 3 (a) Trips system with 2 channels upscale-Hi Ill Hi, or one channel upscale Hi Hi Hi and one channel downscale or 2 channels downscale. j (b) Isolates containment /drywell purge penetrations. 5 (c) With irradiated fuel in spent fuel storage pool. (d) Also isolates the Auxiliary Building and Fuel llandling Area Ventilation Systems. F; (e) With fuel in the new fuel storage vault. (f) With fuel in the spent fuel storage pool. a fj (g) WIth fuel in,the dryer _storagg, area. g ~ :. + b ? I g 1 ii e t f f 3

n, A r 6 5 TABLE 3.3.7.1-1 RADIATION MONITORING INS 1RUMENTAT ON y ~ O MEASUREMENT MINIMUM CpfJtNELS APPLICABLE ALARM / TRIP OPERABLE CONDITIONS SE1 POINT RANGE ACTION c) !.. [ ' INSTRUMENTATION E 1. Component Cooling i*. Water Radiation Honitor 1 At all times $1 x 10 cpm /NA 10 to 10 cpm 70 e.a 2. Standby Service Water System Radiation 5 6 6 Honitor 1/ heat 1, 2, 3'.and* il x 10 cpm /NA 10 to 10 cpm 70 exchanger j train jl 3. Offgas Pre-treatment 3 6 Radiation Monitoi 3 'l 1, 2 15 x 10 mR/hr/NA 1 to 10 mR/hr 70 I 4. Offgas Post-treatment 3 5 6 { Radiation Monitor 2 1, 2 11 x 10 cpm (Hl), 10'to 10 cpm 71 6 $1.0 x 10 cpm (Hi Hi HI) w e IN 5. Carbon Bed Vault 6 ?j ! Radiation Monitor 1 1, 2 1 2 x full power 1 to 10 mR/hr 72 background /NA t .r*, .i 6. Control Room Ventila-2 2 tion Radiation Monitor 2/ trip system 1,2,3,5 and** $4 mR/hr/ 10 to 10 mR/hr 73 ~ 5 mR/hr# e-i 7. Containment and Drywell l L. ') Ventilation Exhaust -2 2 -<2.0 mR/hr/ 10 to 10 mR/hr 74 Radiation Monitor At all times I [ +r P sysien <4 mR/hr(b)# + I 'g 10~2'to 10 mR/hr 75 8. Fuel Handling Area ] Ventilation Exhaust [ 1,2,3,5 and** $2mR/th'r/ Radiation Monitor a./4cip syshm jgp(d)# g u p 9. Fuel Handling Area Pool -2 2 i Sw'eed Exhaust Radiation C Honitor' (c) < 18 mR/hr/ 10 to 10 mR/hr 75 l I L d, 4/teffi s ysk* -<35 mR/hr(d)# M s

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I'N5iRUMENTATICN [ TABLE 3.3.7.1-1 (Continued) RADIATION MONITORING INSTRUMENTATION ACTION ACTION 70 With the required monitor inoperable, obtain and analyze at least one grab sample of the monitored parameter at least once per 24 hours. ~ ACTION 71 ~ With one of the required monitors inoperable, place the a. inoperable channel in the downscale tripped condition within one hour. b. With both of the required monitors inoperable, be in at least - HOT SHUTDOWN within 12 hours. ACTION 72-With the required monitor inoperable, perform area surveys of the monitored area with portable monitoring instrumentation at least once,,per 24 hours., ACTION 73 With one of the required monitors in a trip system inoperable, a. place the inoperable channel in the downscale tripped condition within one hour; restore the ineperable channel to Op5 RAS @ c..T status within 7 days, or, withir. the next 5 hours, initiate and 'C" maintain operation of at least ene control room emergency filtration system in the isolation mode of operation. b. With both 'of the required monitors in a trip system inoperable, initiate and maintain operation of at least one control room emergency filtration system in the isolation mode of operation within one hour. ACTION 74 With one of the required monitors inoperable, place the a. inoperable channel in the downscalm tripped condition within - l one. hour'. ,g b. With two of the required monitorsVinoparable, isolate the l, containment and drywell purge and vent penetrations within 12 hours. ACTION 75 With one of th6* required monitors inoperabl.e, place the a. inoperable channel in the downscale tripped condition within one hour. w.aciegy: tem b. With two of the required monitors inoperable, initiate and ] maintain operaticn of at least one standby gas treatment subsystem within 12 hours. GRAND GULF-UNIT 1 3/4 3-58

-- -- -- ~

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~ = Item No. N TECHNICAL SPECIFICATION PROEI.EM SHEET . Pricrity /./M i Identified By Date Responsible Supervisor E. 3.3,2 /-/ g,gp9 Tcch Spec Refere3ce: .i Problem

Title:

Ahi A -t f'td. Det ).' .D 1. Problem Description (Tech Spec, FSAR SER, GE Design, Other): ML eN 'Npb lb., C.z/1 s.l dl. rL. ,. 2. /' i 2 1 m / / 1 CW) +.. Safety Significance ri '\\]/**. Math- ..Q eN na 4 ful) Spe j.,t y l. ..\\. L \\ \\ g- \\ i h* 2. ~~.,v.- ,a hD I %s w d..a.t..e.) C Q (_ t u ol,-e A.d T'. 3 t_.e Q M -c M \\ u Q oAex c'er s'. A 3 c.\\w.m\\ 5 e P c mOf.,. Wr_ cen\\I \\ x \\ c.ceAl 2 o c ugumWd / '.o ~x\\b-V. o Ao~ Vid Ay s T. 3.* Anticipated Resolution: ', acei.( M %; Chi '" kg 1 Pcc Axr(( ffi sW( 3 4. NRC Response,to Item (NRR/IE): I / tlRG Notified:- Individual Nocified Daee Time 5. Disposition: Items Closed: (How) / Date Time cc: J. E. Cross R. F. Rogers .m..e m.mme 9*

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.r. ~ . <. :.r .. ::~.s '*.5.). '. _.._* r:,. *: e. '._..s z 2_ " TECH S?EC PRIORITT" Punchlist Item # /9 Y Tech Spec 3 /4. 3. 7 ~ __ _1. _ . Priority iN' ,TO: Manager of Nuclear Plant Engineering s.d. 7EOM: Chairman, Prioritization and Disposition Chair:sn L JU.CT; Tschnical Specifications Punch 11st Item i IU PDTS:84/ DQD$- ~ DATE: 3[IC/64- .a - The subject Tech, Spec item has been determined by the Disposition Co=nittee to raquire Engineering support. o C r- + \\e_

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__u. u ..._ a _u m _. __ _. u 2 m. ....... _._...-.-.~ ~ ,/ "TICE SPEC PR!ORI"'T" Punchlist Item # see 41itek,) Tech Spec Se e. ATTAel 2 Priority 5,, A WL 4.3. T0: Manager of Nuclear Plant Engineering FROM: Chair =an, Prioritization and Disposition Chairsan SU3 JECT: Technical Specifications Punchlist Iten # __ se.e ATTa.ck d FDTS:84/ M / k DATE: 7//o/74 'The su'aject Tech ' Spec item has beed dete=ined 37 th'e Disposition Co itf. ee to re quir.: Engineertug support. Dr"AI*.3 : Tb, s \\,9,, s 3, o t, t, 3 w e. o,n e.l v,so, are. ,1,_+. Oe .u,_

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~ ~.. _ _ ~. ~.. o. " TECH S?EC ?RIORITY" ~ MEMO TO: J. F. Pinto, Manager of Nuclear Plant Engineering FROM: C. L. Tyrone, Project Manager

SUBJECT:

Handling of Tech Spec Review Icess ~ 't~-- - 'i-TS1to: 84/C)CQt ~~ DATE: March 11, 1984 This memorandum confir.s our conversation of March 0, 1984 At that ' - ~ time, your assistance was requested in resolving discrep4.ncies on eleven priority 1 items. Since then two items have been added. Thds'e items

• are all *
• previously identified itens which recuire early resolutict with the NRC.

A-response is needed on these ite=s by 12:30 PM on March 1*,1984. " A list is ~ arrached. Furthermore, all items of any priority identified (cr previously known) which are being handled on this program require expeditious handling. This includes areas where requests are originated from other interfacing. c. organizations such as the Plant or Nuclear Se -rices. In any case where conflicts regarding highest priority is not clear, I am available to provide clarification. It is suggested that you arrange 7 day a week. support in this area as it is needed and arrange for all NPE personnel who will be involved in this effort to be available (or on call) in a nanner that vill support the Tech l Spec Review program. p-Y h u 1 SHH: sad Attachment 1 l cc: J. B. Richard (v/a l J. P. McGaughy (v/a) T. E. Reaves, Jr. (w/a) J. F. Pinto (w/a) S. M. Faith (w/a) J. E. Cross (v/a) J. G. Cesare (w/a) T. E. Cloninger (w/a) G. W. Smith (w/a) R. J. Green (v/a) L. R. McKav (w/a) l-R. C. Fron (w/a)

1. C. Surgess (w/a) l D. W. Stonestreet (w/a) 71'e (Tech Spec Records) (w/a) l l

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s. LIST OF CURRENT PRIORITY 1 ITDIS REQUIRING NPE SUPPORT - - -~ PDTS:8,4/ P/L # Date Sent 001 199 002 3/10/84 180 003 3/10/84 033 3/10/84 004 054 005 3/10/84 001 006 3/10/84 016 007 3/10/84 015 008 3/10/84 198 009 3/10/84 202 010 3/10/84 213 3/10Q4 011 219 ,3/10/84 012 083 013 3/10/84 168 3/10/84 L .-( .e o

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y .,... _ _ ~. Attrehm:nt 1 AECM-84/0093' Page 16 DEFINITIONS FOR " CHANNELS", " TRIP SYSTEMS", AND " TRIP FUNCTIONS" FOR RADIATION MONITORING INSTRUMENTATION TABLE 3.3.7.1-1 Trip Unit / Logic / Monitor Parameter Function .o D17-LCRM-K607 Comp. Clg. Wtr. Hi Alarm / Monitor D17-LCRM-K604 SSW Loop A Hi Alam/ Monitor lD17-LCRM-K605 SSW Loop B

• Hi Alam/ Monitor t

t l' D17-RITS-K612 Offgas Pre-treatment Hi Alarm / Monitor D17-LCRM-K601A Offgas Post-treatment Hi & Hi Hi Hi Alarm / Monitor D17-LCRM-K601B Offgas Post-treatment Hi & Hi Hi Hi Alam/ Monitor fD17-LCRM-K601AOffgas Post-treatment f Closes Hi Hi Hi, Inop,or Downscale - - - - - - Both - Offgas. k D17-LC1pi-K601B, Offgas. Pest-tseatment* I .Disch. l , { Hi Hi Hi, Inop or Downscale, l N64-F060 { TRIP k FUNCTION g TRIP SYSTDI I 1 D17-RITS-K611 Carbon Bed Vault Hi Alam/ Monitor D17-RITS-K621A Control Room Vent; Hi Alarm / Monitor D17-RITS-K621B Control Room Vent. Hi Alarm / Monitor ? D17-RITS-K621C Control Room Vent. Hi Alam/ Monitor i D17 -RITS-K621D Control Room Vent. Hi Alam/ Monitor h17-RITS-K621A Control Room Vent. l Isolates CR ~ Hi Hi, Inop or Downscale and Starts CR Both -- Fresh Air D17-RITS-K621D Control Room Vent. t Unit A Hi Hi, Inop or Downscale y i TRIP FUNCTION b t TRIP SYSTEM I I ~ D 7-RITS-K621B Control Room Vent. Isolates CR Hi Hi, Inop or Downscale I and Starts CR l 17-RITS-K621C Both - i Fresh Air D Control Room Vent, Unit B g g Hi Hi, Inop or Downscale J TRIP FUNCTION I TRIP SYSTEM i I D17-RITS-K609A Containment & DW Exh Hi Alarm / Monitor D17-RITS-K609B Containment & DW Exh Hi Alarm / Monitor D17-RITS-K609C Containment & DW Exh Hi Alarm / Monitor D17-RITS-K609D Containment & DW Exh Hi Alarm / Monitor

• 0ne channel (typical of 21 shown on this page) 13sp31

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=.-. ~ AECM-84/0093 Page 17 ^ DEFINITIONS FOR " CHANNELS", " TRIP SYSTEMS", AND " TRIP FUNCTIONS" FOR RADIATION MONITORING INSTRUMENTATION TABLE 3.3.7.1-1 Trip Unit / Logic Monitor Parameter Function l-l tD17-RITS-K609A Containment & DW Exh. Closes Outboard i lD17-RITS-K609D Hi Hi, Inop or Downscale Both Containment Containment & DW Exh. Cr 7 and Inboard I Hi Hi, Inop or Dowriscale Dnwell Cr. 7 Valves I TRIP FUNCTION TRIP SYSTEM i D17-RITS-K6098 Containment & DW Exh. lClosesInboard i Hi Hi, Inop or Downscale Both C incainment g i D17-RITS-K609C Containment & DW Exh. C1 7 and Outboard I i Hi Hi, Inop or Downscale J Drywell Gr. 7 Valves 1 l TRIP FUNCTION I TRIP SYSTDr L I D17-RITS-K617A Fuel Handling Area Vent (1) Hi Alarm / Monitor g--- -g ID17-RITS-K617B Fuel Handling Area Vent

• i (1) Hi Alarm / Monitor i

J D17-RITS-K617C Fuel Handling Area Vent (1) Hi Alarm /Monitot' E ~ D17-RITS-K617D Fuel Handling Area Vent (1) Hi Alarm / Monitor D17-RITS-K618A Fuel Handling Area Pool Sweep Exh (1) Hi Alarm / Monitor D17-RITS-K618B Fuel Handling Area' Pool Sweep Exh (1) Hi Alarm / Monitor D17-RITS-K618C Fuel Handling Area Pool Sweep Exh (1) Hi Alarm / Monitor D17-RITS-K618D Fuel Handling Area Pool Sweep Exh (1) Hi Alam/ Monitor D21-RITS-K622 New Fuel Storage Vault Hi Alarm / Monitor D21-RITS-K623 New Fuel Storage Vault Hi Alarm / Monitor D21-RITS-K624 Spent Fuel Storage Pool Hi Alarm / Monitor D21-RITS-K625 Spent Fuel Storage Pool Hi Alarm / Monitor D21-RITS-K626 Dryer Storage Area Hi Alarm / Monitor Hi Alarm / Monitor D21-RITS-K600 . Control Room +

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(1) Logics, TRIP SYSTEMS, and TRIP FUNCTIONS are shown on page 46 of this attachment under Isolation Actuation Instrumentation Table 3.3.2-1. I3sp32 Y O EF p

an-i ' J w.. V s.* ', l'. W i TECHNICAL SPECIFICATION PP.03LEM SHEET Item Number: 202 Priority: 1A / Identified By Date Responsible Supervisor Tech Spec

Reference:

Table 3.3.7.5-1.4 1 Problem

Title:

Post Accident Monf'oring Instrumentatica 1. Problem Description (Tech Spec, FSAR, SER, GE Design, Other): 12 channels of suppresion pool temp noted in FSAR Tech Spec only reference 6. Should "6,1/ sector" be changed to"12 j/ sector" under " required number of channels"? 2. Safety S1'nificance: FSAR presently lists 12 Tech Specs could*.be'tren-g g conservative in relation to FSAR. 3. A::ticipated Resolution: Further investigation required; submit Tech Spec Change if required. ~ e/d t.4t fgc A. .Sf4C-f4.5 ita's% 6 & (C+ Y ~ c 4. NRC Response to Item (NRR/IE): NRC Notified: / Individual Notified Date Time 5. Disposition: E Items Closed: (How) / Date Time cc: J. E. Cross R. F. Rogers ( (.. e .,.-e.m. pgg y ?' M 9 y e

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Reference:

Table 3.3.7.5-1.4 i Problem

Title:

Post Accident Monitoring Instruentation } 1. Problem Description (Tech Spec, FSAR, SER, GE Design, Other): 12 cliannels of suppresion pool. temp noted in FS'AR Tech Spec on'ly reference 6. Should "6, 1/ sector" be changed to"12, 2/ sector" under " required number of channels"? ^ ~ . 2. Safety Significance: FSAR presently lists 12, Tech Specs could be non - ' conservative in relation to FSAR. 3. Ancicipated Resolution: Further investigation required; submic Tech Spec Change if required. L .i 4. NRC Response to Item (NRR/IE): NRC Notified: / Individual Notified Date Time 5. Disposition: Items Closed: (How) / Date Time cc: J.- E. Cross R. F. Rogers

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Reference:

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Title:

M O' 'O ^'k 'MIC d* 4 G ) 1. Problem Description (Tech Spec, FSAR, SER, GE Design, Other): n cl A } s i,, / Li >../) M 7d-n J ll '4-su)

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.s-.- /.. 't " TECH SPEC ?RIORITT" Punchlist Iten # s, Amek,j Tech Spec Se e. ATTAel ed Priority 5,8 A T%L.),. TO: Manager of Nuclear Plant Engineering FROM: Chairnan, Prioritization and Disposition Chairman SUBJECT,:, Technical Specifications Punchlist Iten i see A'TTa.ckd PDTS:84/.(JO/N p /o M DATE: The s.u' j ect Tech' Spec,ite= has been-deter =ined by the Disposition Co ittee to requir.: Engineering support. DE~ AILS: he, I e.W,_, 1.1. u t. E. s ve. , re.1 v __f o, sre ,f A. r fe,. A,_ Z.11. a, e Te.\\.%.. o a '.Ie s-s : .* /99~ L e_v*, Co. P DTy r t /ae, #

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_e .A. o-e " TECH SPEC PRIORITY" MEMO TO: J. F. Pinto, Manager of Nuclear Plant Engineering FROM: C. L. Tyrone, Project Manager

SUBJECT:

Handling of Tech Spec Review Items ~ ~ TSRO: 84/CCCI DATE: March 11, 1984 This memorandus confirms our conversation of March ;0,1984. ~ At that time, your assistance was requested in resolving discrepa.ncies on eleven priority 1. items..Since then two items have been added. These items are all previously identified items which recuire early resolutien with the NRC. A response is needed en these ite=s by 12:30 PM on March l',1984 A list is attached. Further= ore, all ite=s of any priority identified (cr previously kncun) which are being handled on this progran require expedi,tious handling. This includes areas where requests are originated from'o:hei interfacing' organizations such as the Plant or Nuclear Services. In any case where conflicts regarding highest priority is not clear. I a. available to provide clarification. It is suggested that you arrange 7 day a week support in this area as it is needed and arrange for all NPE personnel who vill be involved in this effort to be available (or on call) in a nanner that will suppor: the Tech Spec Review program. h L SHH: sad Attachment ec: J. B. Richard (w/a J. P. McCaughy (v/a) T. E. Reaves. Jr. (v/a) J. 7. Pinto (w/a) S. M. Feith (w/a) J. E. Cross (w/a) J. G. Cesare (w/a) T. H. Cloninger (v/a) G. 'J. Smith (w/a) H. J. Green (w/a) L. R. McKay (w/a) R. C. Fron (v/a) !.. C. Surgess (v/2) D. J. Secncstreet (v/a) File (Tech Spec Records) (v/a) - - ~ ~ ~ * ' - ~ ~ - ' * * * - * ~ ~ ~ ,%.,ws..+, .+es.-we~~ 'C* . [' s

7. - - - _ . t l} ~ LIST OF CURRDT PRIORITY 1 ITEMS REQUIRING NPE SUPPORT PDTS:84/ pjg, p Date Senc l 199 002 3/10/84 180 3/10/84 003 3 004 3/10/84 54 005 3/1o/34 001 3/10/84 006 016 3/10/84 007 015 3/10/84 008 198 009 3/10/84 3/10/84 010 13 3/10/84 011 1 - 3/10/84 01., 083 3/10/a4 ot3 168 3/10/84 L s. C l l i l-n-w-...~.- - - ~ - - ~- ,r

I ~~ , Attachment 1 a AECM-84/0093 Page 21 DEFINITIONS FOR " CHANNELS", " TRIP SYSTEiS", AND " TRIP FUNCTIONS" FOR ACCIDENT MONITORING INSTRUMENTATION - TABLE 3.3.7.5-1 Transmitter / Sensor Parameter Recorder Function B21-PT-N062A Reactor Vessel Pressure B21-UR-R623A Monitor B21-LT-N091A Reactor Vessel Level B21-PT-N062B Reactor Vessel Pressure B21-UR-R623B Monitor B21-LT-N091B Reactor Vessel Level E30-LT-N003C Supp. Pool Water Level E30-LR-R600A Monitor E30-LT-N003D Supp. Pool Water Level E30-LR-R600B Monitor (a) M71-TE-N012A(B) Supp. Pool Temp. 40* (a) - M71-TE-N022A(B) Supp. Pool Temp. 82* M71-TR-R605A(B) Monitor (a) M71-TE-N023A(B) Supp. Pool Temp. 142* (a) M71-TE-N024A(B) Supp. Pool Temp. 180* (a) M71-TE-N025A(B) Supp. Pool Temp, 262* M71-TR-R605C(D) Monitor (a) M71-TE-N026A(B) Supp. Pool Temp. 318* i I E61-PDT-N014A Ctat/DW Diff. Pressure

• E61-PDR-R601A\\

Monitor. L E61-PDT-N014B Ctat/DW Diff, fr'~ssure "E61-PDR-R601B ~ M5nitor e M71-PDT-N001A Drywell Pressure M71-PDR-R601A Monitor M71-FDT-N001B Drywell Pressure M71-PDR-R601B Monit'r o M71-TE-N013A(B) CRD Cavity Temp. M71-TR-R602A(B) Monitor M71-TE-N008A(B) Drywell Temp. - 166' el. M71-TE-N013C(D) CRD Cavity Temp. M71-TR-R603A(B) Monitor M71-TE-N008C(D) Drywell Temp. - 166' el. E61-AITS-K001A(B) Ctat H, Conc. Analyzer E61-AR-R602A(B) Monitor E61-AITS-K002A(B) DW H Conc. Analyzer 2 M71-PDT-N002A Ctat Narrow Range Pressure M71-PDR-R601A Monitor M71-PDT-N002B Ctat Narrow Range Pressure M71-PDR-R601B Monitor M71-PDT-N027A Ctat Wide Range Pressure M71-PDR-R601A _ Monitor M71-PDT-N027E Ctat Wide Range Pressure M71-PDR-R6013 Monitor .M71-TE-N007A(B) Ctat Temp. - 139' el. M71-TR-R602A(B) Monitor M71-TE-N007C(D) Ctat Temp. - 139' el. M71-TR-R603A(B) Monitor

• One Channel (typical of 28 shown on this page) 13sp36 kN "M's.OM

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~ - )*p' ~ s-g .t , c, e 4 -.4--'...- TECHNICAL SPECIFICA~ ION PROBLEM SHEET

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~ Itenhu=ber: 219 Priority:

1. IA

/ locntified Sy Date Respons:.sie Supervisor Tech Spec

Reference:

Figure 3.4.6.1-1 ~ Problem

Title:

Pressure / Temperature Limit Curves 1. Problem Description (Tech Spec, F5AR, SER, GE Design, Other): The pressure-temperature limit curves do =ct cceply with the closure flaTie pres-sure-t'emperature safety margins in Progra= IV.A.2 of App. G to 10CFR50. Proof ~ and review co= ment from ME3, Dece=ber~ 15, 1983.

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~ _ _.._ :.... p_, _....e. =-.., _...: _.. n. 7.. ._1__ = =- s. 2. Safety Significance: 3. Anticipated Resolution: Evaluate to determine if the figure vill require revision. . b_ 4. NRC Response to Item (NRR/IE): /Vg'A M ' N h d ,t/ff,9 % fM <^Ss a. NRC Notified: / -Individual Jo-dfied . Date Time 5. Disposition: ~ ~ ~ - ^ Items Closed: (How) b 2 ace I1:e f

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