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Note to:
T. Novak From:
E. Adensam
Subject:
GRAND GULF EEN TICKETS i
As you requested, we have tabulated the Grand Gulf Green Tickets. They grow as we speak.
If you wish, we can provide updates as appropriate, or you can have Peggy call up the file at any time. The address is LIST / GRAND GULF GREEN TICKETS.
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GRAND GULF GREEN TICKETS Ticket Date Number Subject Completed Due Date Status 14222 Questions Concerning GG 03/23/84 All but From: Rep. E. J. Markey
. Enc 4 +
To: Chairman Palladino is downtown 14269 Grand Gulf Operating Exper.
04/19/84 04/04/84 From: Commissioner Gilinsky To: Chairman Palladino 14305 Grand Gulf License Review 05/10/84 04/13/84 From: Cc.nmissioner Gilinsky Tot' William Dircks 14306 Requests information con.
04/17/84 Typed Draft Grand Gulf to PM From: Rep. Ed Bethume To: Chairman Palladino 14316 Q's concerning Grand Gulf 04/18/84 Typed Draft Nuclear Power Plant to PM From: Rep. 8. Anthony, Jr.
To: Chairman Palladino 14404 Grand Gulf Restart Decision 05/10/84 05/07/84 Still owe request list of documents info on this From: Commissioner Gilinsky Ticket Item To: William J. Dircks 14438 Grand of full Operating 05/31/84 Assigned to license to GG Nuclear D. Houston Station on 05/22/84 From: Rep. G. V. tiontgomery
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To:
14439 Request to know whether the 05/24/84 5/21/84 electrical power supply systems at GG meet GDC17 From: Conmissioner Gilinsky 14464 Proposed Backfit Rulemaking 6/11/84 (SECY 84-170)
From: Asselstine To :
Denton MAY 31 EB4
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GRAND GULF GREEN TICKETS Ticket Date Number Subject Completed Due Date Status t
14222 Questions Concerning GG 03/23/84 All but From: Rep. E. J. Markey
. Enc-1. 3 --
To: Chairman Palladino is downtown I
1 14269 Grand Gulf Operating Exper.
04/19/84 04/04/84 From: Commissioner Gilinsky To: Chairman Palladino 14305 Grand Gulf License Review 05/10/84 04/13/84 From: Commissioner Gilinsky Tor William Dircks 14306 Requests information con.
04/17/84 Typed Draft Grand Gulf to PM From: Rep. Ed Bethume To: Chairman Palladino 14316 Q's concerning Grand Gulf 04/18/84 Typed Draft Nuclear Power Plant to PM From: Rep. B. Anthony, Jr.
To: Chairman Palladino j
14404 Grand Gulf Restart Decision 05/10/84 05/07/84 Still owe request list of documents info on this From: Commissioner Gilinsky Ticket Item To: William J. Dircks Y
14438 Grand of full Operating 05/31/84 Assigned to i
license to GG Nuclear D. Houston Station on 05/22/84 From: Rep. G. V. fiontgomery
(~c To:
14439 Request to know whether the 05/24/84 5/21/84 electrical power supply systems at GG meet GDC17 From: Commissioner Gilinsky 14464 Proposed Backfit Rulemaking 6/11/84 (SECY 84-170)
From: Asselstine To:
Denton WAY 31 EB4
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GRAND GULF OPEN ITEMS Issues prior to criticality 1
Tech Spec issues (see attached) 2 Staffing concerns 3
Order to modify license
- jj Issues prior to full power 1
Resolution of TDI Diesel Generator issue 2
Resolution of onsite/offsite power enhancement program 3
Agastat relays -
4 Control room leakage 5
Hydrogen control system 6
Reion mini-SALP in response to Commission meeting 2/29/84 7
OtherSSERitems(?)
Other
- 1) Allegations
- 2) Hearing on Amendment 10
- 3) Gilinsky Green Ticket 14269 - Why wasn't the Commission given Frank's Operating Experience memo?
- 4) Gilinsky Green Ticket 14305 - What are we doing to assure MPAL TS review is OK?
2
- 5) Representative Ed Bethume Green Ticket 14306 - Details of G problems;
-who is responsible; When will the plant be fully operational?
- 6) Chilk-o-gram to provide the Commission with the safety significance of the TS problems.
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~. GRAND GULF OPEN ITEMS Issues prior to criticality
- 1) Tech Spec issues (see attached)
- 2) - Staffing concerns
- 3) Order to Modify license i
Issues prior to full power
- 1) Resolution of TDI Diesel Generator issue l
- 2) Resolution of onsite/offisite power enhancement program j
- 3) Agastat relays -
- 4) Control Room leakage
- 5) Hydrogen control system
- 6) Reion mini-SALP in response to Commission meeting 2/29/84
- 7) OtherSSERitems(?)
iss Other
- 1) Allegations
- 2) Hearing on Amend.10
- 3) Gilinsky Green Ticket 14269 - Why wasn't the Commission given Frank's Op Exp memo?
- 4) Gilinsky Geeen Ticket 14305 - What are we doing to assure MP&L TS refiew is OK?
2
- 5) Rep,Ed Bethume Green Ticket 14306 - Details of G problems; who is responsible *,
a When will the plant be m@ for=felloperation.?
- 6) Chilk-o-gram to provide the Commission withtph safety significan%wce 6f the TS problems.
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...~. i 1-GRAND GULF OPEN ITEMS Issues prior to criticality-Y
- 1) Tech Spec issues (see attached)
U r %, --b 2) Staffing concerns dc6 Mh.r- - Region II followup on advisor training program
- 3) Order to modify license Issues prior to full power
- 1) Resolution of TDI Diesel Generator issue
- 2) Resolution of onsite/offsite power enhancement program
- Region II activities: a) Inspection and testing of gas turbines b) Inspection of procedures and training
- 3) Agastat relays - #l& /id f M fe d
- 4) Control room leakage 5)--1975rogen-centrat sysh 1' A.'b
- 6) Region mini-SALP in response to Commission meeting 2/29/84
") Othee-SSER-items-41F .i -] Other i 1 Allegations - non-licensed mechanical maintenance 2 Investigations - qual, card issue (Material false statement) 3 Hearing on Amendment 10 4 Gilinsky Green Ticket 14269 - Why wasn't the Commission given ORAB's Operating Experience memo?
- 5) Gilinsky Green Ticket 14305 - What are we doing to assure MP&L TS review is OK?
2
- 6) Representative Ed Bethume Green Ticket 14306 - Details of G problems; c-I who is responsible; When will the plant be fully operational?
4l
- 7) Chilk-o-gram to provide the Commission with the safety significance of the TS problems.
1 /4;z_,
GRAND GULF OPEN ITEMS Issues Prior to Restart
- 1) Staff decision on adequacy of MP&L Tech Spec review.
2) Issue Order to modify license to correct Tech Spec (Attachment includes licensee proposed changes) Staff to add necessary changes. Issues Prior to Full Power Decision
- 1) TDI diesel generator requirements for full power operation.
- 2) Credit which can be allowed for onsite/offsite power enhancement program
- Region II activities: a) Inspection of testing of gas turbines b) Inspection of operator training and operating procedures for gas turbines.
- 3) Staff approval of replacement schedule for Agastat relays.
- 4) Acceptability of control room leakage.
- 5) Region II update of SALP evaluation.
- 6) Commission decision on need, if any, for additional staffing requirements.
- 7) Region II response on adequacy of OTEC technical advisor exams.
Other
- 1) Allegations - non-licensed mechanical maintenance 2)
Investigations - qual, card issue (Material false statement)
- 3) Gilinsky Green Ticket 14269 - Why wasn't the Commission given ORAB's Operating Experience memo?
- 4) Gilinsky Green Ticket 14305 - What are we doing to assure MP&L TS review is OK?
2
- 5) Representative Ed Bethume Green Ticket 14306 - Details of G problems; who is responsible; When will the plant be fully operational?
- 6) Chilk-o-gram to provide the Commission with the safety significance i
of the TS problems. t /o 3
.~ GRAND GULF OPEN ITEMS Issues prior to criticality c. t r.;, i. y h, m. n o S ?> i
- 1) Tech Spec issues (see attached) _
[ d2w,agt/,O4 ( v '.. - j
- 2) Staffing concerns.'
g( 2 n., s j
- 3) Order to modify license
( 1 !j Issues prior to full power i
- 1) Resolution of TDI Diesel Generator issue
~
- 2) Resojution of onsite/offsite power enhancement procram hdu J NAM '-
- 3) Agastat re Wys -
/ 4 % @ y*#f i P 9
- 4) Control room leakage s
Hy$onmini-SALPinresponsetoCommissionmeeting2/29/84 '^@Dj. h 'f' "'. drogen control system 5 6 R 7 OtherSSERitems(?) I --~ a S ' ' ' ' ' ^ Other -;
- r a -
c ^
- 1) y qd e- ;a.3.y%.< J - f +'" d '-~' >* < ~L hN a$1'd f%.dabny c2) Hearing on Amendment 10 I
e3) Gilinsky Green Ticket 14269 - Why wasn't the Commission given A...:2'// 8'S Operating Experience memo? Og ' 4) Gilinsky Green Ticket 14305 - What are we doing to assure MP&L TS review is OK? 2
- 5) Representative Ed Bethume Green Ticket 14306 - Details of G problems; who is responsible; When will the plant be fully operational?
- 6) Chilk-o-gram to provide the Commission with the safety significance of the TS problems.
) i i J 1 i d w
3 x FOOTNOTES - SECTION 2 FSAR INCONSISTENCIES Page.1 o fiOTE ISPS # PRIORITY SAFETY SIGNIFICANCE COMMENTS l 1 319 M-2E Tech Spec Base's references wrong code - i date for Rx vessel. Change 1974 code to 1971 Edition thru winter 1972 Addendum. l 3fdM4 W 75 - -,7'to7I,FS465Eg Change FSAR and SER from 112.5% to 118% 2 151 5 l for APRM trip. Tech Spec is correct. &c 50) be-7.s s em s-1 [Rss) M M *a. -Jg E?a p~ez J<< ~,e d (r., p..g j + ~ ~ u ng,.,,_., cfB T 'c N %,/. /t. %,,;s,.,,,J./ f L* *)s q <,.l. i i e i ~ e Wisd1 Rev. 3, 4/11/84 k%
FOOTNOTES - SECTION 3/4 FSAR INCONSISTENCIES NOTE TSPS # PRIORITY Page 1 of SAFETY SIGNIFICANCE 1 152 COMMENTS 2E [c Pg} 7"L'# -<v "' ' " " '" ' [' h FSAR to be revised to.28% delta k/k c,.. - <.-/ m.m, e, Jr I/, 714 E ~ </~/. shutdown margin. Tech Spec is more conservative. 4 805 3B k/k shutdown margin.FSAR now states.25% e corrected for sodium pentaborate required volume. Tech Spec shows 4,587 gallons; FSAR shows 4,170 gallons. 5 313 28 0 "' b Tech Spec 4.1.5.d.4 changes " Heaters" to " normal heater". SLC tank has only one 3 A [e' "] "'"'"', *' ' ~ ~ ~ ' ".M d i. < C I' '- - " " ' ' " ' ' ~ " ~ ' ' heater for maintaining temperature. 6 300 A ,4j,[ert}b J C p gg., a Change FSAR MAPLHGR Limit at 20,000 MWD /T 7 800 3B[M .-f 3 a., c...<< M & T w p le 4 4" to read 12.6 kw/ft (Table 6.3-6). o r f r. # e.,) tr8CS} p<fd</.fn I., 4-a . y > <' Change FSAR APRM scrampoint. 8 806 0y et% L.}... w m.g 2 - X* % c) A ~ p s + - 3.2.2 vs FSAR Table 7.6-6. Tech Spec 3B[c pg y ga # */,f,,, y,,f, , ;,,,, j,,7 g gg,
- /
MCPR limit of 1.18 in Tech Spec is correct. Change SER Section 15.4.3. ?3 201 d 2B [Ec d h -'c J,.a..J~~,sy,G, ejse 1a,a!r Fuel load error analysis is not limiting. I , A,. g f2tf "e_6. Table 3.3.2-1 change is to delete note (f) for secondary contai isolation valve groups. nment manual Mechanical QS$ vacuum pumps do not trip on manual 18[~r"'l A p ~ 6o isolation initiation. 25 076 94 75ce...'.f< r. Jr! F J 4 4 ppg-This inconsistency is in ECCS response times between FSAR & Tech Spec. LPCS/ LPCI to be 40 sec. 28 802 3B (( tsp] /e e - TS L o J. Change FSAR to state 40% of rated thermal fjf5D]/1,%.<*A {1 E % j1 s u ' a Np c~'l power for RPT-E0C function; now states - -a 30% power. 9.,t.,s air e 4- 0 ?.,,... < w. WIsd2 Desaw.*IM # * * ' * * - ~^ ~~
~ FOOTNOTES - SECTION 3/4 FSAR INCONSISTENCIES Paw fiDTE TSPS # PRIORITY SAFETY SIGNIFICANCE COMMENTS \\ 2B[/h
- hJ-, [ ISE "' '""" "
Clarification of which revision of ^~' 91 335 [ prs] M N ~ ' '# - f ' # '"*'# Regulatory Gui.de 1.137 applies. Proposed f( fPc f.i3 7. c e.< / 15.<* ~< #MT.7^C"/.F''/^'srequi rementschange to include diesel, fu '"'l a;pc %, w 4,4.:,, TM. dr -- -- < ^ " Check for water. h/"-hf/ c,...;LrnM e t-k']SJ~T~?'$5AR. nh.pf. eq~uired to describer.J-- A l 4 E
- se.
93 810 3B me...... J, 7.54 4 s'acwut:+as setpoints per DCP 82/3173. [T5 3.] V"A ' m.,-r,M Mgr~.4 FSAR Q&R 040.5.c needs to agree with Tech Spec 4.8.4.1. [#,.? ) 809 5 s 94 6 /,9 3B {pSg] p,f / /,,, J,. 7 z ggg m nd SER should be changed to properly Me M0V thermal overload A 102 249 2D FSAR does not address GGNS use of a vendor to perform solidification / dewatering of radwaste. 2E f?f8) M ^# I'18 7* f"*
- * ~ "
'"#~" 107 322 Change to ADS Bases page 3/4 5-2. Change _,T1.. J q / *-<-, m 4. / c 4 ~ 7,,/, /3,.. / r ~. f the Bases with respect to LPCS/LPCI injection pressure into the vessel. b-% hy [* l j a..,. G, u, i. L c 04 Change to state that the reactor pressure c is reduced by ADS substantially below the pressure at which LPCI/LPCS inject into the vessel. 2E[CI'#ll. S"'" ' ',,k./ " O * " *t'^ *#f*"l*-'" 109 320 Page 3/4 6-4 of the Rases has an .,, / /0 6 0.p, % * 'rc f3y,,) f_ fs /, f,v p,,,. /. incorrect number of 1089 for blow down pressure. Should be 1060 psig which i reflects 105% heat balance. i 119 291 3B Maximum MSIV Isolation Times - Allowable times differ in FSAR and Tech Spec. W [4.... 6 c.,< >. d, : [Cf3)hoA<p]<. 125 019 2B c Drywell Purge Flowrate Definition - Tech Spec definition is in CFM, should be SCFM cb -r,.< (,<, /lir / r 4.C. (i.e., temperature dependent). [C38))lnt/J: t r y,y. s Hlsd5 Rev. 3, 4/11/84 / r.y <1/. r e..,/ ,, f f.,,/
FOOTNOTES - SECTION 3/4 FSAR INCONSISTENCIES Pass ' f!0TE TSPS i PRIORITY SAFETY SIGNIFICANCE COMMENTS [MN 151 812 3B / " ' ' / ' ' / ' #'"- INEL item 38. ---1-T-T hner i s d 816 3B ef .e/',,. ,b./p ) Nmlues for MSL Flow-j High setpoint and rangemanao. [RSS2 C" 153 820 3B /"fr " rM" ef +</ 2, -fA4). RCIC Instrument settings in FSAR Table j 7 7.4-1 differ from Tech Spec setpoints. h,[154 819 3B 617 reference to 61 response m ordgrs is incorrect. , 1y Should be spectrum analyzer.
- T,155 818 3B Revise sWNPB.2.3.2 to indiaate that t
'*-- 2ra also used to isolate secondary containment. 156 817 38 .Rev - +a indicate tha h has capability to overcome the additional inleakage from a single 4 inch penetration or failure of all non-Q lines 2 inch and under. (
- TBD.
157 3 ~ Revis M 1 to correct the fire i N w level alarm. i
- To Be Developed Ulsd5.1 Rev. 3, 4/11/84 s
- v.,
FOOTNOTES - SECTION 5.0 FSAR INCONSISTENCIES Pa e p lTE TSPS 8 PRIORITY -SAFETY SIGNIFICANCE COPMENTS 2D [/ k M ' " N 7 '" b M 7*/ * ' lllegible figures. y 225 2E[/AO)" 2 105 es ' p Correction of terminology for effluent ,i release boundary vs. unrestricted area , bounda ry. 3B[CSB]/7r-M((..,c.4, A% / fgfrf4f,2 t{ . The figures for containment and drywell 3 25? i: l net free air volume in the FSAR are not
- j 4g-g- f[, <e si ame M4e /ec-**W the same as those in the Tech Spec.
l; 4 be # / 2 f( A p g. " 'A.//c, M (.Pe>= 2. 7 E5Within the FSAR the numbers are not 7 gpJ. 4p* ' l VEG g]).{CSD))%'dh)csju.af / consistent among Tables 1.3-4, 6.2-1,, l J 6.5-6. t 6 258 3B [csay A q 4 4,, jt%,,,,,,,,,,, /r,- drained if the valves (G41-F032, F033) The spent fuel pool can be partially f-J4 c+/e+l 7.4,,. are opened while the spent fuel pool gate [ I [dgp]ft, D k,',/3 %) A h m q %1/~( f is removed. The valves are neither j i locked nor do they have electrical l n, lAJ W.- ge.../ f,3 /,'../ p s p< J ~' ' d interlocks to prevent inadvertent mj,r., sLj. operation. 7 259 28 GGNS Tech Spec Table 5.7.1-1, Vendor Documents, and FSAR Table 3.9-1 do not l correlate. The transients / cycles' are ~ defined differently in the documents. l' I jl,f d-c.. i c. -1. - c/.[4 I Rev. 3, 4/11/84 l Wisd6 1
' ~ ~ A ~ FOOTNOTES - SECTION 6.0 FSAR INCONSISTENCIES Pa ~ N0fE TSPS #~ PRIORITY SAFETY SIGNIFICANCE C0petENTS s w 13 813 3B Requirement for HQA are less restrictiv'es. li in the 0QAM than in the GGNS Tech Spec. b ] MQA is required by GGNS Tech Spec to be a merber of the SRC. ll .i l r 16 096 2E FSAR requires semi-annual review of ALARA l appraisals by SRC. 2E[ del %]M Nup66 -0737wp[ - 4 ~? qA Verify GGNS Tech Spec, include NUREG-0737 f. 19 270 requirement. (IIT. D./. /J I sJk-4 m T f L4 I e t I if, 1 I i I Rev. 3, 4/11/84 l Wisd7
~.... h k-9,~,,i h., Ic 4 e t. ATTACHMENT 5 L. 3 Matrix Footnotes 'so'rted by. SER dis'crepancies. This is' responsive to the SER portion of List 1 (task la of 3/26/84 NRC memo). Safety significance column is incomplete. .V i e 9 e ? .]q 't n
- ~
q e'l 'l it. 1i e i 4 i e
- W hv*
- eme * +
a w3-.e.,._,m,.. .%g,, .x , _, +,,,
~ w -... FOOTNOTES - SECTION 2 SER INCONSISTENCIES
- g..
Pa b HOTE TSPS # PRIORITY SAFETY SIGNIFICANCE COPMENTS w 1 1 319 2E Tech Spec Bases references wrong code 'N, date for Rx vessel. Change 1974 code to 1971 Edition thru winter 1972 Addendum. j ? 151 3B [I c5B] plm 7 5.a %,,, g Change FSAR and SER from 112.5% to 1181 i for APRM trip. Tech Spec is correct. i- [c PD) TS L e at J a aa,.*,tGj,,5 9 q...Ys, f. rin 'l 1 i l !. -?( C 1 i i s %~ l i i j. Wisd14 Rev. 3, 4/11/84
- =
m-e we, -- e %w - ee
. _. w... .. x.. ad...a~: - wd'
%
- - ~ ~ - - " " " " ,w FOOTNOTES - SECTION 3/4 SER INCONSISTENCIES P 't i NOTE- \\' TSPS # PRIORITY' . SAFETY SIGNIFICANCE-CO M NTS .g e 3B h * [ I b - ',"'*< # A M j] 8 806 MCPR limit of 1.18 in Tech. Spec is [C PBJ % A rJpf.p c, 44 /, qu
- 2.,.I,, < z r Z..<-/ A correct. Change SER Section 15.4.3.
e ele **fa$ e f,_, 5 7.,7 < A, Fuel load error analysis.-is not limiting. me,- 28 [I GF) dr n. de.,p r/g aI',,._,,f;, 23 201 e t Table 3.3.2-1 change is to delete note (f) for secondary containment manual i . isolation valve groups. Mechanical i vacuum pumps do not trip on manual isolation initiation. i d a,b 38 ygy } k <.e,J. m,7I, f 7,.f, SER 8.4.4.1.d requires maximum and f~ 29 147 p 3 minimum limits for second-level voltage i sensors and time delay devices. Table [L 3.3.3-2. 3B[f3.,.,f nfSE) O#"dd 'Y I 7' SER does not properly describe Diesel 89 808il as,, 61 .s.. .,-.c W al- /' ./- Generator trips under emergency / 4/<. r.m ,( 2^. 4 ty D. c. W,, 7Q4 conditions.. Val p e Lu),,.,e';lI,.,o g M,L< m.<J. t 94 809 3B' FSAR and SER should'be changed to properly describe MOV thermal overload bypass circuitry, L 3AffSB] M h "* '#' # 7' & '4 "'7^'7' SER ' requires Turbine stop/ control ' valve 111 148a L"* 2/- O "* ' 'f '.4/, by-weekly testing. ,4 4 f,,,t.cc. 4 _tj. a.-en su 4 /* 'I '*/'"N"' ' ,/,,,, j Q,g n n s ~ L. 9"/% 1S ' ,,,, y p it,,,.... <p< ~ 3 ~- i i i 5 Rev. 3, 4/11/84 ~ ~...
FOOTNOTES - SECTION 6.0 SER INCONSISTENCIES P ~ -j s -.0TE TSPS # PRIORITY f1 SAFETY SIGNIFICANCE COMMENTS 095)'// .F 2E g 2 10l[ 2E Correct Organization Chart in Tech Specs l' and FSAR. 3 340 il 2I Revise to require an eight hour break as f opposed to a twelve hour break. 3B(44 l%] TI 12 814 " Ad y r </le dem M 564 SET requirements for SRC composition are j 4 j in conflict with the GGNS Tech Spec. 2E,[/3 _t-J / tera 75 t-/ dg4 gg b, 7g SER requires Tech Spec to control work in 20 146 0 the control room ceiling in other than cold shutdown. i I h i; I Im 1 f r. Wisdl6 Rev. 3, 4/11/84 t
FOOTNOTES - SECTION 3/4 FSAR INCONSISTENCIES . NOTE TSPS # PRIORITh Page 3 SAFETY SIGNIFICANCE 56 257 2B COMMENTS The Action Statement b of Tech Spec 3/4.4.2 is inconsistent with 3.6.3.1 Action Statement b but is more conservative in that it requires mode switches to shutdown immediately at a pool temp of 105"F with a stuck open 1' valve where the FSAR and Tech Spec 59h'001 3.6.3.1 allow the temp to go to 110*F. IB[ON^'T'd 0 F i:. e, p e,- h..... ADS 7 vs. 8 valves. s 67 229 2BfA sB] C m x ff4 e,.r,,, ],.y. t. t-)< ',. M "l* T*r .m !N 4<n.e i al. : l,rJ. i,,Jp, n TA r J. 4.6.1.4.a.2 and c.1 revise for q.,/ ; t Is' clarification. inboard system, not on outboard asMSIV L 3B [/ M " h N "d implied by STS.
- u.-
69 801 a A Evaluate equipment qualification program to confirm CTMT to. Auxiliary Building 3BI-[SQ flo df"-".'M. Diff. Press. Range. Revise FSAR and ^~ '" E c NUREG-0588 response. 70 260 j,, w s,., sa. g,, [esa),ff'ef' coE'. -..r l fd,..hm.,] ys ', r, i-<.,%. <4 %,,,,,,.p CTMT avg. air temp. 80 F vs. 90*F. p..q i + FSa n P Correct FSAR. -72 17 [ I bC ~^ -/~- 'd tcr e u' " ".y s a,e' d'Y I #d# r e s. A/ c is not leakage. Clarification. 74 234 3A[~Ic53] fler - 7/S u. e vac< I FSAR revisions to agree with Tech Spec. Tables for Sup. Pool Volume and instrumenta tion. Editorial for clarification of suppression pooI level instrumentation. 85 131 2G Table 3.7.6.5-1 requires update for hose stations for completenes's. 3B[fsh]/l f h^h' 'L 'I "' ~ ~M ^'1" ' / h /9 R - 88 804 This is an inconsistency with the FSAR g,-J..:IT, T S <../ s E R <..<,....'l<..r j f,s N P u. only, not the SER. Later evaluation determined Tech Spec and as-built to be ey/> 1 c e, n.,id,,(>., J r..,.., / :,,..,,,. u tb . rf c,...fffMcorrect and revision of FSAR is needed. Diesel day tank volume needs to be corrected. Hisd4 y /4. 3 /1:, e, a jn s A ~~j, *. ' / n. i r9
- s Rev. 3, 4/11/84
= - - - - -- - ~ ~
) \\ FOOTNOTES - SECTION 3/4 FSAR INCONSISTENCIES Page -p0TE' 'SP: PRIORITY SAFETY SIGNIFICANCE COMMENTS 34 10 3 pw. 3Bh1E7B]2:~/'#" '3 ' " ' ' '# I'
- g g m,,,,( 4, a g.J <<,.,e/ a ) r e s.../<.</.
d Tech Spec Tab.le 3.3.7.1-1 and FSAR Table d / 11.5-1 do not maten. (Rad Mont. Inst). ,1 Consider explanatory note as addition ~ to I FSAR. i 39 807 t'M 3B ptE7S/ %e d M " [/"r d'7"*-'#h"/'"i " FSAR Cha , _.,/) M -. ,,j'< /p e g, - f m.-, /,r S Z ;v r. 's intervals (Sections 11.5.2.3.1; nge to show proper Surveillance 11.s.2.3.2;12.3.4.2.7). 40 202 38 Table 3.3.7.5-1. Proposed change t increases the number of required channels i of suppression pool temperature monitoring from 6 (1/ sector) to 12 {2/ sector). 41 327 38 Change FSAR requirements for CTMT/DRWL d area rad monitor inst to be sent to ei vendor for calibration each refueling Ph 4r outage. 9 h aC@
- IC M
}% m,.,,f] m.'.ht-2 4f5ARn:. Scia'. 43 t Y J'.4,;, / s'A 6
- 2. 3./ <h e. -eI'ef>>6h < t/). e.rS Revise Tech Spec to require post accident a
' b'. uc44 ro be u,f u 4',-, 7,'(,,.. rad monitors to be operable in Conditions e 1, 2, and 3 to agree with STS. ^ 44 330 t' 2B [
- T 9^'5 d '" * ' #'
'"i E > #- /##"' # j i. ' ' Table 4.3.7.5-1. Proposed change adds. -ne -/Jy 4Jp L.., fn 4.f. 4 5 7. p>ru aep.(~ i ^*'j W/.J..r - #, (, f./. 4.',,f w a,r. <. ".I,ic /ri. co,- / daily checks to accident monitoring instrumentation.
Reference:
FSAR
- A b'Y (j,,,,,,',.Jf.. ale.nc-N'YG T' ' ' d * I l
- 0
- I *
- I *
%. 2fh/eg'" " '[ h ' '"' ' ' ' '/,,,r '/. ,7,., 7.,i. The.7 cps was approved by Amendment 12 47 251 and issued by NRC is now inconsistent with the FSAR. 49 010 28 l T(3!} y,,,//,..a <,,,,...',,.'y 'TEl% ? A' N 7 "'l%,f
- ,_ y,,.... I,. le f r i. [C l'/$ 7%'s.
' ' ! " I' */ Plant has 5 TIPS vs. 3 as stated in Tech ~~ c u - Spec. Change Tech Spec to 5. 52 073 2B 102 2B Table 3.3.7.9-1. Update Table of fire 304 2D detection instrumentation and zones in both Tech Spec and FSAR. Wisd3
sNETCH'$HEET ^ ~ ~[ ^~ WESTINGHOUSE ELECTRIC CORPORATION r-5 n, k. (@ T5 PS of n.c.., L. ' > _) I - 7~t: 0 aur m Y S&W" k T '"
- itod eg 20c u - y W. -
y = e m FS A a 10 h "M u _,, we c c w y ya - 7n-- . T S a reda _ pj ,p, A s-y "ud f TY' W - -T ,: Mo % 5 % "*~ L % r,,% s.u w x - S E lf h3 Ts P5 g42,44 ) 'T54 wsd. ~'W h @ *+4 S lx A e s s* % y - g~q 6 m du. ~r spfa n up.x, I I I I a i l8h -y p ..---_.-_..m ,,yy .r,
/ outy.3 nra_ hor.; ry t b or te. / i I g... 4 ATTACHMENT 4 Matrix Footnotes ' sorted for FSAR discrep5ncies.' This is responsive to the FSAR portion of List 1 (task la of 3/26/84 NRC memo). Safety significance column is incomplete. )W n Ub YLsw 2-9 ] { L $ 3 w i s{ ,An.)ft,.<,,y, :,, E i., l / m. p % d ' h *r.-l / , N c ] %p+~e, >[% 7,- [c S g} (,.,C 3 j~r DC - zo, C,9 e...: : ; r,, c./ n, ' .,..,4, ,_p /o f u Ir..i fSfLs.,' g y (q G 'f, / D7 ) 2. C, 1 ?, / 2 't, j / s I l]Of / 7/ 'L.04,23C,2.3I,'?32,'L Y /
- /
/ / 3 2 7 h ~l 4 't 321 (S a < i9,17t,?sz,zco,32d i Gk SN y lv,k..-/* is ~, * ', y '7AL.f1 c,. [, f,,,,n his,,., ,g p,, g,, g [xc sB] A 33 (4/ 7/rt M *'} g,,~),., p3,4Rl TS..,~~ >I>%'-r W5 ? LO),'chwyi 1 rs av r use. (" '33 ^ 3 "* "/"'"'"' pp,,, ps><ips 4~ b'r (G% vr 4 ' ':t q 5 nu & FS#' [t c Srj c L ey th *-/1 C h. oog/ ofy / 0J ~1"', A gpst Ja f 7 a, (=SMP L.~;A r y / 4 g )<> }m - /o 7
e =8 FSR f. neo). L -bl*k O,i u x 1 c > 1.o,. J 1.,. O Ts A y onn>7 s 4 ~ n w s,- q m e c.c c s
- i 50 C"lo 14
/ '7/ vs 1 X SE R n TS f ) h A p & > /, l :.._ ___ ? I33 , ~.! ~ $' < ppsjif n ,*u.' 1 U h $d v- /s l f
- 2. I :_
yo _. s ,a 3 4*l + zz7 j Uk u1 .3 L,.:...a. CR 4 p.,a-u O g(, :. 2 1y mi .m /O f
s. -4 .. y'% / e. ~ f 4 ny j *. O u'y I .i v,c.,,3 go 4 1 ATTACHMENT 7 t Matrix Footnotes sorted by FSAR vs. As-Built discrepancies. This is responsive to List 3 (task Ic of 3/26/84 NRC memo). Safety significance column is COMPLETE. / .( 9 e Y /df ~ v e ,,, - -,. - +,. - --,a, .x.
%a - w N INCONSISTENCIES: FSAR vs. AS-BUILT PLANT Page 1 of i Y. 110TE TSPS # PRIORITY SAFETY SIGNIFICANCE COMMENTS y/ 2B 52 073 Smoke detection is provided for subject areas.
- a. FSAR 9A.7.2.2.24 and 69 states that 102 28 Overall SER conclusions not impacted.
smoke detectors will be installed. sh 2D[/bil%J/2e no, /02 ( Jog e/J'4A-/ g,,/,4,4,4..tme, The as-bullt plant has these detectors i 304 . >N N /x.E,4./<./ A TL*,* 7%f4 -rs, ~., v. w., r d installed. FSAR is not current. ryu..t:cr ~ y Purely editorial. Renaming of zones does not
- b. FSAR Figure 9A-22 does not correctly alter fire protection requirements or measures identify fire detection zones. The provided. Overall SER conclusions are not design documentation does identify the impacted.
zones correctly. (Applies to diesel generator buildings.) 74 234 3A The FSAR discussion should be expanded to clarify The FSAR 6.2.7.5 does not clearly reflect g reference to narrow range instrument. The the suppression pool level y clarification of the high and low water level instrumentation, i.e., which instrument alarm input should not alter overall conclusions provides high and low level alarms. in the SER (7.5.2). Narrow range instrumentation not described. Arrangement of sensors requires clarification. 85 131 2G Second column line is an editorial error. There FSAR Figure 9.5-4 incorrectly lists a can be only one location for a single hose second column line for a single hose I station. Area is provided necessary fire station. ,D protection measures. No impact on SER overall 4/%.. O/), f h,c 34 L;.u M,NN~. d'M f ^. 7g' p p.n]t,'t.q conclu;fons. 94 809 / 3B (Evaluation of item under review.) FSAR 7.1.2.c.22 does not fully describe Y g methods used for providing thermal overload protection to M0V's. 112 234 3A The FSAR discussion should be expanded to clarify FSAR 6.2.7.5 does not clearly reflect f reference to narrow range instrument. The the suppression pool level 'i/ clarification of the high and low water level instrumentation, i.e., which instrument 9 alarm input should not alter overall conclusions provides high and low level alarms. in the SER (7.5.2). Narrow range instrumentation not described. Arrangement of sensors requires clarification. W3sdl Rev. 3, 4/11/84 i
INCONSISTENCIES: FSAR vs. AS-BUILT PLANT Pags, a "1.. fl0TE TSPS # PRIORITY SAFETY SIGNIFICANCE COMMENTS -?p v.. 154 819 3B By MP&L/Bechtel evaluation, the key issue is that FSAR Table 3.7-17 incorrectly describes ' 5)q prompt readout of seismic information is provided certain seismic instrumentation. The ./ c _ in the control room. The current design, with-as-built plant has response spectrum u-4 h 'Af 6j g - overall conclusions are not impacted. //-p6A r analyzers, meets this requirement. The SER analyzers not recorders, J2/ w.I,>_. 1.n a, 55 818 /p 3B Barriers such as these are considered acceptable, FSAR does not indicate that blind flanges g based on MP&L/Bechtel evaluation of BTP CSB 6-3. and rupture discs are used in secondary 9 The omission of the discussion of the use of containment boundary (FSAR 6.2.3.2). blind flanges and rupture discs does not impact the overall SER conclusions (SER 6.2.2). Categories "a" through "f" include discrepancies bmerous corrections and clarifications 158 306 ' 'm IB l g which are purely editorial, dealing with proposed to FSAR Table 6.2-44, f 9) information or changes to information which do " Containment Isolation Valves." The not bear significantly on the overall acceptance l items fall into the following categories: l of the plant's containment isolation provisions.1 l a) Penetration sizes incorrect or not p ') 0 (, {CSE) c h '":t d?klG Up.- ywr%, g., le w indicated in Table. e -r
- 6b /*
Md4A*s)f>ue-/ Tf b) Divisional power supply incorrectly ,v t.., ( 3 o -> <.:. ).o m., a J. j?,, p, g 73 j,,, 3aye;eg, '3 M M c'.t/ -"/.'<-~ /l.t;,J, ,4 c) Valves incorrectly labeled as inboard or outboard. [cIB) g,t,,,,/v/ gjjg j 4 j j,,,1, !.,, d) Direction of flow in line incorrect".
- eli-f/eli e) Footnotes no longer referenced in Table should be deleted, f) Valve position under certain fl
- l%),J.u l,L,/ w m )<<
circumstances not expressed consistently throughout Table (e.g., " Closed" vs. " fail closed"). (Justification for Category "g" changes under g) Isolation signals of some valves Q /Jo. 2 c., /2-s A (i > v review) listed incorrectly.
- ~
&q e 14., owl. ' ~? FL 'O' - Nc
- O 4*b~'''
gc x.c a.-r w ~ M. (1d & - a rc nic or % yA w A 6 /,/2. ($wc~~G4 e e t v c '} - 5 e ei-i> e '. ~ f D
- E. h
/.. Rev. 3, 4/11/84 W3sd2 i
- $~"4
['o UNITED STATES / ) g { g NUCLEAR REGULATORY COMMISSION /fj g E WASHINGTON, D. C. 20555 / t o +... Docket No. 50-416 p MEMORANDUM FOR: Elihbr G. Adensam, Chief Lichnsing Branch No. 4 Division of Licensing FROM: M. D. Houston, Project Manager j Licensing Branch No. 4 1 Division of Licensing 9.
SUBJECT:
FORTHCOMING MEETING WITH MISSISSIPPI POWER & LIGHT COMPANY j REGARDING TDI DIESEL GENERATORS, ONSITE/0FFSITE POWER ij ENHANCEMENT, STATION BLACK 0UT AND PRA CONSIDERATIONS i DATE & TIME: May 7, 1984 1:30 PM - 4:00 PM LOCATION: Room P-ll4 Phillips Building Bethesda,. Maryland PURPOSE: To discuss the MP&L response to the staff request of April 25, 1984, on TDI Reliability. PARTICIPANTS:(1) NRC MP&L T. Novak B. Cavanaugh I, F. Miraglia J. Richard ' 1 F. Schroeder J. McGaughy R. W. Houston L. Rubenstein C. Berlinger ~ M. D. Houston, Project Manager j Licensing Branch No. 4 ] Division of Licensing j cc: See Next Page } Meetings between NRC technical staff and applicants for licenses are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC ] Staff Policy", 43 Federal Register 28058, 6/28/78. .i //O t
P e. n. ,,l j' t GRAND GULF DIESEL POSITION (ALL 1984) April 25 Staff Letter to MP&L Requesting Diesel Inspection before exceeding 5%. May 6 MP&L Submittal: a. Proposal Submitted (1) Diesels are reliable for first fuel cycle (2) Ascend in power; operate at 100% (3) Perform diesel inspection at first RF0 b. Alternate Proposal (1) If staff concludes diesel reliability uncertain, perform diesel inspection during startup program (up to 85% power) May 18 Mtg. with MPL a. Staff position wrt. May 6 proposal: (1) TDI diesel must be inspected prior to exceeding 5% power. (2) MP&L submittal does not demonstrate adequate reliability to meet GDC 17; nor to justify operation. b. Staff conclusions (1) Staff determined plant is safe for 5% power operation for same period: required enhanced onsite AC power - (2) Consistent with Shoreham decision, an exemption was required to be submitted (within about 7 days). Required safety bases for any continued operation (at 5% or higher). (3), Decided to order a teardown inspection of one TDI diesel; enhanced gas turbine reliability; teardown to commence promptly. /// L
,t GRAND GULF TECHNICAL SPECIFICATIONS REVIEW The NRC staff and its consultant the INEL Laboratory (EG&G, Inc.) has reviewed the Grand Gulf Unit 1 Technical Specifications (T.S.) to verify that they were properly derived from the analysis and evaluation included in the Grand Gulf Final Safety Analysis Report (FSAR) as reviewed in the NRR staff's Safety Evaluation Report related to operation of the Grand Gulf Plant. Comments and recommendations resulting from the NRR review were presented in meetings with your representatives on April 4 and 5, 1984. Comments and recommendations regarding T.S. resulting from earlier reviews by NRR and RII were provided to your representatives in a January 24, 1984, meeting, and as handouts in a meeting on March 22, 1984 (memorandum from R. C. Lewis (RII) to D. G. Eisenhut (NRR), and NRC Inspection Report 50-416/84-06. In response to the NRC staff's request, your representatives have provided a table listing Problem Sheet Numbers for those above-identified NRC comments, most of which are included in the Grand Gulf Technical Specification Review Program (GG TSRP) (Enclosure 1). As identified in Enclosure 1, some of the NRC comments were not included in the GG TSRP as of April 10, 1984. In meetings with your representatives, there were two other requests made for additional information: (1) Additional information regarding certain MP&L license amendment requests which are under review by NRR technical staff was discussed and NRR comments were provided as handouts in meetings on March 20, and March 28,1984,(2) Based on the NRR staff review of the 248 Problem sheets provided to the staff in a March 14, 1984, meeting, there are 66 problem sheets which appear to require resolution prior to plant operation in excess of 5% //a
. (Enclosure 2). These problem areas are currently considered by your representa-tives as not requiring resolution before exceeding 5% power. The problem numbers of Enclosure 2 were provided to your representatives in meetings on April 5. Additional _ problem areas to be considered were identified by staff in Region II in the April 11, 1984, meeting. We also need more information than is provided on MP&L TSRP problem sheets regarding certain problem areas (Enclosure 2) to determine whether the staff agrees with MP&L that these T.S. 4 problem areas do not need resolution prior to exceeding 5% power. Finally, we need any new and revised problem sheets resulting from the MP&L TSRP, in addi-tion to those already provided in the MP&L April 4, 1984, meeting with NRC. The NRC staff has arranged meetings with your repres.ntatives on April 20, April 27, May 4 and May 11, 1984, to discuss responses to the above identified 1 information. We need information regarding those technical specifications which the NRC staff has identified as potential T.S. changes prior to exceeding 5% power which are not yet in the MP&L TSRP and therefore, have not been designated as problem areas by MP&L (Enclosure 1). I request that you make available sufficient engineering and operations personnel to resolve in a timely manner the many technical specification problem areas identified by NRC staff and in your Technical Specification review program. + Spicifically, we would like to discuss with your appropriate technical personnel, those T.S. areas identified in Enclosures 1 and 2 which you are not currently considering for resolution prior to exceeding 5% power operation. Others may need to be considered as we complete our review of priority for resolution of problems identified in problem sheet numbers greater than 248.
~ 3-We have not noticed meetings for the next four findings, beginning tomorrow April 20, 1984. Your prompt and substantive response to this request is needed to assure the necessary changes to Technical Specifications are made
- j prior to consideration of the issuance of a full power license.
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i o UNITED STATES g jg NUCLEAR REGULATORY COMMISSION e WASHINGTON, D. C. 20555 ..... f" Docket No. 50-416 Mr. J. P. McGaughy Vice President Nuclear Production Mississippi Power & Light Company P. O. Box 1640 Jackson, Mississippi 39205
Dear Mr. McGaughy:
Subject:
NRC Staff Review and Processing of Grand Gulf Technical Specification Changes for a Full Power License Amendment The Mississippi Power & Light Company (MP&L) letter dated April 19, 1984, pro-vided the final MP&L report on Grand Gulf Technical Specification review pro-grams. A total of 405 problems were identified in this report which were found during the past year and in a special MP&L Technical Specification Review Pro-gram begun in March of this year. There were 11 additional problems identified as a result of other NRC reviews, and these were provided in an MP&L letter dated May 1,1984. The resolution of the problems is being tracked by MP&L by assigning a Technical Specification Problem Sheet Number to each problem. In your report, you have concluded that the resolution of most of the problems requires technical specification changes, but that some of the problems may be resolved by changes to the Final Safety Analysis Report (FSAR) or by justifi-cation of existing Grand Gulf Technical Specifications on an engineering or operational basis. The NRC staff is reviewing this report and the associated Technical Specifica-tion Problem Sheets. As discussed with you recently, all Technical Specifica-tion changes identified on problem sheets will be required for full-power operation. For those changes MP&L recommends deferral until after full-power operation is authorized, or those changes MP&L considers unnecessary, adequate justification must be provided in writing. The enclosure outlines the review procedure that will be used for MP&L submittals and NRC review of these changes. Your cooperation in implementing this procedure is requested.
~ Document Name: /- LTR MCGAUGHY Requestor's ID: HELEN Author's Name: E. Adensam Document Comments: REV & PROCESSIflG 0F GG TS CHANGES FOR FULL PWER LICENSE AMDT l l P l [ i I i l I l i
4., g LICENSING STATUS OF GRAND GULF 1 ~ Grand Gulf Unit I was issued a low power (5%) license on June 16, 1982. Fuel loading was carried out in July through early-August 1982 and the plant achieved t initial criticality on August 18, 1982. The licensee undertook an extended outage from October 1982 until September 1983 upon discovery of inadequate i drywell cooling following non-nuclear heat up. Activities that were completed i during this outage included installation of additional drywell cooling capacity, ~i resolution of deficiencies in surveillance procedures and technical specifica-tions, modifications to a number of plant systems originally on a schedule for completion during the first refueling outage, and recovery from a fire in the Division I diesel generatnr room. Unit I returned to criticality on September 25, 1983, to rasume low power testing which was completed up to 5% power on November 8, 1983. At the conclusion of low power testing, the licensee began a recertification program for the licensed operators. This program.resulted from a Region II inspection as a follow-up on reported discrepancies in the operator qualification cards. The program was completed in late February 1984 and on the basis of a follow-up inspection, Region II has approved the status of licensed operators (with some specific exceptions). There are now sufficient approved licensed operators to support five shift operation. On April 18, 1984, the NRC issued an Order which required the incorporation of certain changes into the plant's Technical Specifications prior to the unit being operated at a power level of up to 5%. Upon completion of the Order's specified actions regarding training and procedure revisions associated with the prescribed j Technical Specification changes, and after performing seismic modifications to j the containment /drywell personnel air locks' pneumatic supply systems, Unit I was taken critical on April 22, 1984. Being limited to 5% power, the licensee is reperforming low power testing on systems that were modified during the last outage, while taking advantage of the neutron flux to rejuvenate their startup sources. FSAR REVIEW (FULL POWER LICENSING) 1. TDI Diesel Generators 14 Grand Gulf has standby emergency diesel generators manufactured by Trans-america Delaval Incorporated (TDI). As a result of a crankshaft failure in a TDI unit at Shoreham in August 1983, the staff performed an in-depth evaluation of the manufacturing and performance history of the TDI units at nuclear and non-nuclear facilities. A large number of operational problems were identified and ouality assurance deficiencies were noted at the manufacturing plant. Taken together, these problems significantly reduced the staff's level of confidence in the reliability of all TDI diesel generators. d 4
LICENSING STATUS OF GRAND GULF The licensee is pursuing resolution of this issue in two ways. First, they have joined a TDI Owner's Group, and jointly are engaged in a program to address the problem areas needing resolution to restore confidence in the TDI diesels. The staff was provided the details of the Owner's Group program on February 24, 1984. Plant specific details will be provided after the staff has approved the Owner's Group program. Second, the licensee has undertaken an enhancement program to improve the reliability of the onsite/ offsite power system at the facility while awaiting resolution of the TDI issue. The staff was provided the details of the enhancement progran in a submittal dated February 26, 1984. A review is presently being performed of MP&L's letter dated April 18, 1984, which addresses the NRC staff's concerns about this program which were discussed in a meeting with the licensee on April 5, 1984. Subsequent meetings on April 13 and 18, 1984, were held with MP&L to discuss TDI diesel generator reliability issues. Unable to conclude that the TDI diesel generators are sufficient to support operation of Grand Gulf Unit 1 at power levels in excess of 55 of full power, the NRC (in a letter dated April 25,1984) has requested additional engine disassembly and inspection. 2. Technical Specifications On March 9,1984, the licensee met with the staff to discuss their current program to perform a complete review of the Technical Specifications. This review resulted from the re-review of the Technical Specifications by the staff and the licensee. Significant discrepancies were discovered which required resolution prior to proceeding with full power licensing. The results of the current program were presented to the staff on April 4,1984 Approximately 350 problem areas have been identified. The staff is meeting on an almost daily schedule with the licensee to assist in the resolution of these problems. Since the licensee has yet to submit the bulk of the proposed changes to the Technical Specifications, an anticipated completion time for resolution is not possible to predict at this time. HEARINGS 1 The Grand Gulf OL proceeding was uncontested. A low power license for Unit I was issued in June 1982. Five weeks later, a single petition to intervene by the State of Louisiana was filed seeking to raise issues regarding the environmental impact of the nuclear fuel cycle. The petition was denied by the Licensing Board and the denial was affirmed by the Appeal Board. In addition, there is an OL amendment proceeding pending. The amendment involves changes to Technical Specifications on operability range for high pressure core spray, automatic tripping of RHR jockey pumps and one time exceptions to ADS trip system surveillance requirements and scram discharge volume surveillance require-ments to allow startup testing. The amendment was issued 9/23/83, after the staff made a final no significant hazards consideration finding. A petition to intervene on the amendment was filed by Jacksonians United for Livable Energy Policies (JULEP). Contentions were filed on 2/15/84 with a prehearing conference . - ~. _. _.. _.. ~
+- -=- o LICENSING STATUS OF GRAND GULF held on 2/29/84 In order issued on April 23, 1984, Petitioner was admitted as a party and the 2 contentions involving one time exceptions to the ADS trip system and scram discharge volume surveillance were admitted for litigation. Discovery has commenced and status reports on hearing preparation and suggested dates for hearing are to be filed 8/1/84. JULEP also petitioned the Conmission on March 29, 1984, to institute a proceeding pursuant to 2.202(a), requesting revocation of the low power operating license and denial of a full power cperating license for Grand Gulf Nuclear Station Unit 1. This show cause petition is presently under NRR Review. 4 NRC INSPECTIONS The preoperational and power ascension inspection program has been implemented and is current at Grand Gulf. In addition to the normal Inspection Program, special inspections to assess the effectiveness of adherence to procedures, the utilization of consultants and advisors, and the level of compliance with regulatory requirenents and license conditions have been conducted to assess the operational readiness of the facility for full power licensing. These have included: (1) Low Power Test Results; (2) Surveillance Procedures / Technical Specifications; _(3) Licensed Operator Qualifications; and (4) Facility Perfo rmance. The results are summarized below: 1. Low Power Test Results Precoerational and acceptance test results were reviewed by on-site inspection. Only four tests were not closed by the inspection staff. One test, "Isophase Bus Ventilation Heat Load" cannot be completed until the plant achieves 100% power, in that the test requires full electrical output to demonstrate acceptability. One test, " Balance of Plant Piping Expansion Monitoring" has been judged sufficiently complete for proceeding to operation above 5% power. Two tests, " Balance of Plant Piping Vibration Monitoring" and " Transient Test Equipment Verification" will be reviewed after the licensee has completed their evaluation of the results. The results from the re-performance of low power testing (on recently modified systems), which is presently under way, will also be reviewed when they 1 become available. 2. Surveillance Procedures / Technical Specifications ? Corrective actions have been initiated by MP&L and the NRC staff to correct specific and generic problems associated with the Technical Specifications and surveillance testing which the staff identified during the period of October 1982 to December 1983. NRC staff members have met with MP&L manage-ment on numerous occasions to ensure that corrective actions taken by MP&L were commensurate with the magnitude of the related problems and that such actions are implemented in a time frame that will minimize their inpact on the public.
LICENSING STATUS OF GRAND GULF As stated previously, approximately 350 problem areas were identified during the Technical Specification review conducted by the licensee, consultants and the NRC. Uncertainties raised from scce of these problem areas resulted in the issuance of an April 18, 1984 Order, which required changes. to selected Technical Specifications to prevent the potential for urdue risk to the public from operation of the facility up to 5% power. Although the a q'. remainder of the problem areas did not require a resolution prior to operation at a power level of up to 5%, they will be corrected prior to ,1 issuance of a full power license. On-site inspections of surveillance i].I procedures have been completed. The procedures are considered to be adequate. 3. Licensed Operator Qualifications The program to recertify licensed operators included an extensive examina-tion and evaluation by the utility of all licensed operators and training in the areas of identified weaknesses. This specific progran began in November 1983, and was completed in February 1984. The recertification program included an individual walk-through oral examination of each licensed operator on each of 78 systems listea on the Grand Gulf licensed operator qualification card. These examinations were monitored by Mississippi Power and Light, representatives of two other utilities, the Nuclear Steam Supply vendor (General Electric), and the NRC. At the completion of this examination process, the records of the licensed operators were reviewed by a Grand Gulf recertification board consisting of plant management. The board examined operator training records and the results of the examinations, and orally examined operators as necessary. Upon completion of licensee recertification process, the NRC independently re-examined all licensed operators. Twenty-three of the twenty-six operators examined by NRC passed. The twenty-three operators provic'e sufficient staff for full power operation. The three operators who failed have been removed from licensed duties as confirmed by NRC letters dated i February 29 and March 23, 1984. 4. Facility Performance '1;j. The level of NRC inspection activity at Grand Gulf continues to be approxi-mately 200% of previously budgeted hours. The inspections have concentrated 1-in those functional areas rated as Category 3 during the last SALP period, a September 1,1982 - September 30, 1983. Our special assessment of the performance since that time is surinarized below: 9 } Plant Operations - The period of actual operation at criticality or up a. I to 5% power has been limited to the conduct of the low power test j program, which began on September 25, 1983, and terminated on November 8, 1983. Low power operation and testing continued throughout October 1983 'and was witnessed by various Region II inspectors. In the judgement of Region II, these operations were conducted in a safe, . go ap4ma.,- we eme. page eawe no,e*+e. - m. ma W m.=,N - - + < * * * - -+ ~ ~ " " * ' "
~ .. a. ~:- . ~ -. - - LICENSING STATUS OF GRAND GULF. deliberate and professional manner, and were very successful. Only tnree unplanned scrams, of minor significance, occurred during this period. That number is less than typical for facilities in this phase of startup. The plant was restarted on April 22, 1984, and is presently operating within its authorized power level of less than 5%. MP&L has taken significant actions, which are responsive to correction of areas of concerns that were identified in the SALP report. Some of the actions taken are: (1) Completed a major operator recertification program and 23 of 26 licensed operators successfully passed the subsequent NRC requalification examination. The recertification program is described in Region II meeting summary dated November 23, 1983, which documents MP&L's November 18, 1983 presentation of the program to Region II. (2) Implemented an extensive Operational Enhancement Program, which among many other items required sensitization of operators to meticulously comply with regulatory requirements, including procedures. This program is described in the March 11, 1983, letter AECM-83/0177 from MP&L to Region II. (3) Conducted system and simulator training of Shift Advisors and Shift Technical Advisors. These advisors underwent written examination and review of their performance and experience by the plant's Operator Training Evaluation Board. (4) Completed a comprehensive review of Technical Specifications with identification and planned resolution of all known discrepancies. The program is described in MP&L letter AECM-84/0183 to NRR. (5) Management plant personnel changes involved replacements of both the Plant Manager and the Assistant Plant Manager for Operations, with individuals having previous nuclear commercial operating experience. The plant organization has been restructured to incorporate three Assistant Plant Managers for better management
- control, b.
Maintenance - Management meetings have been conducted with the highest level of corporate executives to relate NRC concerns for the control of maintenance activities. Licensee activities have included providing specialized training to maintenance personnel in the areas of diesel generators, control rod drive mechanism, and instrumentation and control. During recent weeks, the staff has noted increased actions on the part of both plant and corporate management to ef#ect corrective actions. The staff expects significant improvements in this area. Nevertheless, current elevated levels of inspection effort will
- continue, l
... ~ -... ; :. .u. -. .a. u~ i1 \\ c ~ LICENSING STATUS OF GRAND GULF Surveillance Procedures - As stated in paragraph 2 above, there has c. been significant improvement in this area. d. Quality Assurance The Grand Gulf QA program is considered better than average, but due to lack of effectiveness, as evidenced by-the large number of problems identified at Grand Gulf, the SALP rating in this area was Category 3. The deficiencies identified in the last SALP report have been addressed by MP&L Management., :The licensee has stated that activities are in progress for improvement. Recent NRC inspections have verified that some direct observation of field activities by QA is occurring. However, it is felt,that further increase in this area by QA is warranted. ALLEGATIONS In addition to the above issues, there are presently two allegation files open for the Grand Gulf facility. These allegations were referred to the Office of Investigations by Region II. One of the investigations has been completed and is currently under review by the technical staff, and involves possible falsifica-tion of Operator Qualification Statements. The second allegation is currently under active OI investigation. OI INVESTIGATIONS WARNING -- This information may not be released outside the NRC without the permission of the Director, 01. Internal access and dissemination must'be on a need and right-to-know basis. At present, there is one (1) ongoing investigation involving the Grand Gulf facility which pertains to maintenance training record discrepancies. .., ~... _ _. _... _. _ _..
d. ~. GRAND GULF UNIT 1 SIGNIFICANT ISSUES (FULL POWER LICENSING) 1. TDI DIESEL GENERATOPS - TDI OWNERS GROUP PROGRAM IS BEHIND SCHEDULE. A 2.206 PETITION BASED ON TDI PROBLEMS WAS FILED ON 4/10/84. AN ACCEPTABLE INSPECTION PROGRAM WAS DESCPIBED BY THE STAFF IN 4/25/84 LETTER TO MPal. MP8L RESPONSE AND PROPOSED ACTION SUBMITTED ON 5/6/84. CURRENTLY UNDER STAFF REVIEW. 2. TECHNICAL SPECIFICATIONS - CURRENT MPal REVIEW PROGRAM HAS IDENilFIED AFFROXIMAIELY 400 TECHNICAL SPECIFICATION PROBLEM AREAS. COMPLETE DRAFT MARKUP OF TECHNICAL SPECIFICATIONS SUBMITTED BY MP8L ON 5/9/84. STAFF REVIEW 0F MARKUP TO BE COMPLETED BY 5/25/84. FORMAL TECHNICAL SPECIFICATION CHANGE SUBMITTALS BY MP8L EXPECTED FROM 5/21/84 TO 6/22/84. ALL CHANGES NECESSARY FOR FULL POWER OPERATION TO BE ISSUED IN REVISION TO TECHNICAL SPECIFICATIONS WITH FULL POWER LICENSE. 3. HYDROGEN CONTROL - INTERIM FULL POWER OPERATION JUSTIFIED wilH CONilNUIN6 RESEARCH PROGRAM AND MP8L COMMITMENT PP0 GRAM +'l ',,. ~?>"'"'ANB00WNERS GROUP (HCOG) TEST PROGRAM IN 1/4 SCALE TEST FACILITY WILL ADDRESS OUTSTANDING ISSUES (STARTING IN 9/P4), 4. LICENSED OPERATOR DUALIFICATIONS - RECERTTFICATION PROGRAM FOR LICENSED OPERA 10RS COMPLEIED WITH REGION II REVIEV IN LATE 3/84. CURRENTLY, SUFFICIENT LICENSED GPERATORS TO SUPPORT FIVE SHIFT OPERATION. 5. ALLEGATIONS - PRESENTLY TWO ALLEGATION ISSUES REMAIN. THE FIRSI CONCERNS POSSIBLE FALSIFICATION OF nPERATOR QUALIFI-CATION STATEMENTS. THIS HAS BEEN CLOSED THROUGH REGTON II AND HAS BEEN TURNED OVER TO THE DEPARTMENT OF JUSTICE FOR FURTHER STUDY. A SECOND CONCERN HAS BEEN TURNED OVER TO 01 FOR FURTHER INVESTIGATION, //f
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HELEN ' AUTHOR'S NAME:' DHOUSTON/HMC DOCUMENT COMMENTS: GPAND GULF UNIT 1 SIGNIFICANT ISSUES _e. s 'i f a + ? E s 1 i .F 'j ' k r r i e
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t Pk / M m /lA LICENSING STATUS FOR GRAND GULF 1 Grand Gulf Unit 1 was issued a low power (5%) license on June 16, 1982. Fuel loading was carried out in July through early-August 1982 and the plant achieved initial criticality on August 18, 1982. The licensee undertook an extended outage from October 1982 until September 1983 upon discovery of inadequate drywell cooling following non-nuclear heat up. Activities that were completed during this outage included installation of additional drywell cooling capacity, resolution of deficiencies in surveillsnce procedures and technical specifica-tions, modi.fications to a number of plant systems originally on a schedule for completion during the first refueling outage, and recovery from a fire in the Division I diesel generator room. U7it I returned to criticality on September 25, 1983 to resume low power testing which was completed up to 5% power on flovember 8,1983. At the conclusion of low power testing, the licensee began'a recertification program for the licensed operators. This program resulted from a Region II inspection as a follow-up on reported discrepancies in the operator qualification cards. The program was completed in late February 1984 and on the basis of a follow-up inspection, Region II has approved the status of licensed operators (with some specific exceptions). There are now sufficient approved licensed operators to support y b.C five (5) shift operation FSAR Review (Full Power Licensing)
- 1) TDI Diesel Generators Grand Gulf has standby emergency diesel generators manufactured by Transamerica Delaval Incorporated (TDI).
As a result of a crankshaf t failure in a TDI unit at Shoreham in August 1983, the staff perform d an in-depth evaluation of the manufacturing ar,d performance history of the TDI units at nuclear and non-nucir?' facilities. A large number of operational prob'6; e identified and quality assur-ance deficiencies were noted at th-uf ' uring plant. Taken together, these problems significantly reduceu the staff's level of confidence in the reliability of all..TDI diesel generators. The licensee is pursuing resolution of this issue in two ways. First, they have joined a TDI Owoer's Grcup, and jointly are engaged in a program to address the problem areas'needing resolution to restore confidence in the TDI diesels. The staff was provided the htails of the Owner's Group pro-gram on February 24,.1984. Plant specific Jetails will be provided after the staff has approved the Owner's Group program. Second, the licensee has undertaken an enharcement program to improve the reliability of the onsite/offsite power system at the facility while awaiting resolution of the TDI issue. The !.taff was provided the details of the enhancement program //f
Licensing Status for Grand Gulf in a submittal dated February 26, 1984. Staff concerns about the program were discussed with the licensee on April 5,1984 and are expected to be t submitted by letter on April 13, 1984. The resolution of these issues islO p 4 " ^' expected to be comp lleted by mid-May 1984 i kth~ p.~2 A lw 2 4 -
- 2) Technical Specifications On March 9, 1984, the licensee met with the staff to discuss their current rW #
program to perform a complete review of the Technical Specifications. This p' g @ review resulted from the re-review of the Technical Specifications by the staff and the licensee. Significant discrepancies were discovered which required resolution prior to proceeding with full power licensing. The results of the current program were presented to the staff on April 4,1984. Approximately 350 problem areas have been identified. The staff is meeting on an almost daily schedule with the licensee to assist in the resolution of these problems. Since the licensee has yet to submit the bulk of the proposed changes to the Technical Specifications, an anticipated completion I time for resolution is not possible to predict at this time. j Hearings The Grand Gulf OL proceeding was uncontested. A low power license for Unit I was issued in June 1982. Five weeks later, a single petition to intervene by the State of Louisiana was filed seeking to raise issues regarding the environ-mental impact of the nuclear fuel cycle. The petition was denied by the Licensing Board and affirmed by the Appeal Board. In addition, there is an OL amendment proceeding pending. The amendment involves changes to Technical Specifications on operability range for high pressure core spray, automatic tripping of RHR jockey pumps and one time exceptions to ADS trip system surveillance requirements and scram discharge volume surveillance requirements to allow startup testing. The amendment was issued 9/23/83 after the staff made a final no significant hazards consideration finding. A petition to intervene on the amendment was filed by Jacksonians United for Livable Energy Policies. Contentions were filed on 2/15/84 with a prehearing conference held on 2/29/84. There has been no determination on whether intervention will be permitted and a hearing held. Jmergency Preparedness There are no outstanding emergency preparedness issues for license issuance. {mA .A gp The annual emergency drill was conducted on April 10-12, 1984 CAT Inspection There are no CAT inspections planned for this plant. This type of inspection was initiated by the staff subsequent to the issuance of the Grand Gulf license. -,,m~-
6 Licensing Status on Grand Gulf NRC Inspections The p'reoperational and power ascension inspection program has been implemented and is current at Grand Gulf. In addition to the normal Inspection Program, special inspections to assess the ef,fectiveness of adherence to procedures, the utilization of consultants and advisors, and the level of compliance with regulatory requirements and license conditions have been conducted to assess the operational readiness of the facility for full power licensing. These have included: (1) Low Power Test Results; (2) Surveillance Procedures / Technical Specifications; (3) Licensed Operator Qualifications; and (4) Facility Perfor-mance. The results are summarized below: 1. Low Power Test Results Preoperational and acceptance test results have been reviewed by on-site inspection. Only four tests have not been closed by the inspection staff. One test, "Isophase Bus Ventilation Heat load" cannot be completed until the plant achieves 100 power, in that the test requires full electrical output to demonstrate acceptability. One test, " Balance of Plant Piping Expansion Monitoring" has been judged sufficiently complete for proceeding to operation above 5% power. Two tests, " Balance of Plant Piping Vibration Monitoring" and " Transient Test Equipment Verification" will be reviewed after the licensee has completed their evaluation of the results. 2. Surveillance Procedures / Technical Specifications Corrective actions have been initiated by MP&L and the NRC staff to correct specific and generic problems associated with the Technical Specifications and surveillance testing which the staff identified during the period of October 1982 to December 1983. NRC staff members have met with MP&L management on numerous occasions to ensure that corrective actions taken by MP&L were commensurate with the magnitude of the related problems and that such actions are implemented in a time frame that will minimize their impact on the public. Although errors were identified during the review conducted by the licensee consultants and the NRC, none of the errors (in the judgment of the NRC staff) are of a level of safety tignificance which need to be corrected prior to reactor restart. All identified errors will be corrected on a schedule commensurate with their need (a) prior to issuance of a full power license, (b) during power escalation, or (c) by the 1st refueling outage. On-site inspections of surveillance procedures have been completed. The procedures are considered to be adequate. 3. Licensed Operator Qualifications The program to recertify licensed operators included an extensive examina-tion and evaluation by the utility of all licensed operators and training in the areas of identified weaknesses. This specific program began in
h Licensing Status for Grand Gulf November 1983, and was completed in February 1984 The recertification pro-gram included an individual walk-through oral examination of each licensed operator on each of 78 systems listed on the Grand Gulf licensed operator qualification card. These examinations were monitored by Mississippi Power and Light, representatives of two other utilities, the Nuclear Steam Supply operator on each of 78 systems listed on the Grand Gulf licensed operator qualification card. These examinations were monitored by Mississippi Power and Light, representatives of two other utilities, the Nuclear Steam Supply vendor (General Electric), and the NRC. At the completion of this examina-tion process, the records of the licensed operators were reviewed by a Grand Gulf recertification board consisting of plant management. The board examined operator training records and the results of the examinations, and orally examined operators as necessary. Upon completion of licensee recertification process, the NRC independently reexamined all licensed operators. Twenty-three of the twenty-six opera-tors examined by NRC passed. The twenty-three operators provide sufficient staff for full power operation. The three operators who failed have been removed from licensed duties as confirmed by NRC letters dated February 29 and March 23, 1984. 4 Facility Performance j The level of NRC inspection activity at Grand Gulf continues to be approx- { imately 200% of previously budgeted hours. The inspections have concentra-ted in those functional areas rated as Category 3 during the last SALP period, September 1, 1982 - September 30, 1983. Our special assessment of the performance since that time is summarized below: a. Plant Operations - The period of actual operation at criticality or up to 5% power has been limited to the conduc'. of the low power test program, which began on September 25, 1983, and terminated on November 7, 1983. Low power operation and testing continued through-out October 1983 and was witnessed by various Region II inspectors. In the.iudgment of Region II, these operations were conducted in a safe, deliberate and professional manner, and were very successful. I Only three unplanned scrams, of minor significance, occurred during i this period. That number is less than typical for facilities in this phase of startup. { l MPL has taken significant actions, which are responsive to correction of areas of concerns that were identified in the SALP report. Some of the actions taken are: (1) Compieted a major oparator recertification program and 23 of 26 licensed operators successfully passed the subsequent NRC requali-fication examination. The recertification program is described in Region Il meeting summary dated November 23, 1983, which documents MPAL's November 18, 1983, presentation of the program to Region 11.
r 3 Licensing Status for Grand Gulf (2) Implemented an extensive Operational Enhancement Program, which among many other items required sensitization of operators to meticulously comply with regulatory requirements, including procedures. This program is described in the March 11, 1983, letter AECM-83/0177 from MP&L to Region II. (3) Conducted system and simulator training of Shift Advisors and Shift Technical Advisors. These advisors underwent written examination and review of their performance and experience by the plants' Operator Training Evaluation Board. (4) Completed a comprehensive review of Technical Specifications with identification and planned resolution of all known discrepancies. The program is described in MP&L letter AECM-84/0183 to NRR. (5) Management plant personnel changes involved replacements of both the Plant Manager and the Assistant Plant Manager for Operations with individuals having previous nuclear commercial operating experience. The plant organization has been restructured to incorporate three Assistant Plant Managers for better management control. b. Maintenance - Management meetings have been conducted with the highest level of corporate executives to relate NRC concerns for the control of maintenance activities. Licensee activities have included pro-viding specialized training to maintenance personnel in the areas of j diesel generators, control rod drive mechanism, and instrumentation and. i control. During recent weeks the ',caff has noted increased actions on the part of both plant and corporate management to effect corrective actions. The staff expects significant improvements in this area. Nevertheless, current elevated levels of inspection effort will con-
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Surveillance Procedures - As stated in paragraph 2 above, there has been significant improvement in this area. 1 3 d. Quality Assurance .k The Grand Gulf QA program is considered better than-average, but due 1 to lack of effectiveness, as evidenced by the large number of problems 1 identified at Grand Gulf, the SALP rating in this area was Category 3. The deficiencies identified in the last SALP report have been addressed i by MPL Management. The licensee has stated that activities are in d progress for improvement. An NRC team inspaction is in progress-during { the week of April 9,1984, and the results will be available by 1' April 13, 1984. Increased direct observations of field activities are l in evidence. i i i ~ ..,.m
) l 1.icensing Status for Grand Gulf i Allegations In addition to the above issues there are presently two allegation files open for the Grand Gulf facility. These allegations were referred to the Office of Investigations by Region II. One of*the investigations has been completed and is currently under review by the technical staff, and involves possible falsification of Operator Qualification Statements. The second allegation is currently under active 01 investigation. OI Investigations i At present there is one (1) ongoing investigation involving the Grand Gulf j facility which pertains to maintenance training record discrepancies. WARNING-- This information may not be released outside the NRC without the permission of the Director. 01. Internal access and dissemination must be on a need and right-to-know basis. i i k
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."2 GRAND GULF GREEN TICKETS Ticket Date Fumber Subject Completed Due Date Status 14222 Questions Concerning GG 03/23/84 Dowtown From: Rep. E. J. Markey To: Chairman Palladino 14269 Grand Gulf Operating Exper. 04/19/84 04/04/84 From: Commissioner Gilinsky To: Chairman Palladino 14305 Grand Gulf License Review 05/10/84 04/13/84 From: Commissioner Gilinsky To: William Dircks 14306 Requests information con. 04/17/84 Typed Draft Grand Gulf to FM From: Rep. Ed Bethume To: Chairman Palladino 14316 Q's concerning Grand Gulf 04/18/84 Typed Draft Nuclear Power Plant to PM From: Rep. B. Anthony, Jr. To: Chairman Palladino 14404 Grand Gulf Restart Decision 05/10/84 05/07/84 Still owe request list of documents info on this From: Commissioner Gilinsky Ticket Item To: William J. Dircks 14438 Grand of full Operating 05/31/84 In Concur-license to GG Nuclear rence Chain Station Sent to OELD From: Rep. G. V. Montgomery on 06/01/84 To: Chairman Palladino 14439 Request to know whether the 05/24/84 5/21/84 electrical power supply systems at GG meet GDC17 From: Commissioner Gilinsky To: William J. Dircks //F
.3-s;a _ GRAND GULF GREEN TICKETS (Con't) 2-Ticket Date Number Subject Completed Due Date Status 14464 Proposed Backfit Rulemaking 06/11/84 Assigned to (SECY-84-170) - Grand Gulf D. Houston 4 's From: Commissioner Asselstine on 05/31/84 To: H. R. Denton pqua.h s. t, t, e ?d lV k k + .} != [$ 4
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,m [ / / GRAND GULF GREEN TICKETS Ticket Date Number Subject Completed Due Date Status 14222 Questions Concerning GG 03/23/84 All httt From: Rep. E. J. Markey . Encl. 3 To: Chairman Palladino is downtown 14269 Grand Gulf Operating Exper. 04/19/84 04/04/84 From: Comissioner Gilinsky To: Chairman Palladino 14305 Grand Gulf License Review 05/10/84 04/13/84 From: Comissioner Gilinsky i To: William Dircks 14306 Requests information con. 04/17/84 Typed Draft Grand Gulf to PM From: Rep. Ed Bethume To: Chairman Palladino 14316 Q's concerning Grand Gulf 04/18/84 Typed Draft Nuclear Power Plant to PM From: Rep. B. Anthony, Jr. To: Chairman Palladino 1 14404 Grand Gulf Restart Decision 05/10/84 05/07/84 Still owe request list of documents info on this From: Comissioner Gilinsky Ticket Item To: William J. Dircks + l 14438 Grand of full Operating 05/31/84 Assigned to .i license to GG Nuclear D. Houston Station on 05/22/84 ~l From: Rep. G. V. Montgomery To: ? 14439 Request to know whether the 05/24/84 5/21/84 lt electrical power supply systems at GG meet GDC17 From: Comissioner Gilinsky i 14464 Proposed Backfit Rulemaking 6/11/84 (SECY 84-170) From: Asselstine To: Denton M7 }
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