ML20245B676

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Responds to Re Status of Implementation of TMI Action Plan Items.All Control Room Corrective Actions Needed to Adequately Protect Public Health & Safety Completed
ML20245B676
Person / Time
Issue date: 06/15/1989
From: Zech L
NRC COMMISSION (OCM)
To: Markey E
HOUSE OF REP.
References
TASK-***, TASK-TM NUDOCS 8906260014
Download: ML20245B676 (23)
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  • i NUCLEAR REGULATORY COMMISSIOMaylor JMartin DMossburg

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  • JBlaha NRCPDR

, \ . .%... */ June 15, 1989 TMurley/JSniezek FMiraglia CHAIRMAN JPartlow DCrutchfield i FGillespie EJordan GHolahan The Honorable Edward J.11arkey MVirgilio  ;

United States House of Representatives JRoe ..

Washington, D. C. 20515 EBeckjordh  %{

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Dear Congressman Markey:

WRussell

  • i i

SEbneter In your letter of March 23, 1989 you expressed concern about the  !

NuclearRegulatoryCommission's[NRC's)oversightoflicensee 1 implementation of TMI Action Plan items and requested our response  !

to several specific questions. As I informed you on May 4, 1989, I when I provideo the NRr staff's response to your question con- )

cerning the status of implementation of Till' Action Plon items at  ;

the Seabrook plant, the NRC stait undertook a detailed review of I

.the status of Till Action Plan items at all licensed power reactor facilities to ensure that our response to your questions would be as accurate as possible.

1 To accomplish this review, the staff requested each nuclear power plant licensee to identify the TMI Action Plan items considered i complete and to provide projected completion dates for all items that remain to be implemented. Copies of the individual licensee i responses to that request were provided to you by my letter of 1 April 27, 1989. After comparing the licensee information with our l own records, we have prepared an updated list of the TMI Action i Plan items that remain to be implemented as of May 19, 1989 (Enclosure 1). We are also providing you a description of the review process and the criteria we used to determine whether the items should be considered implemented or still open (Enclosure 2) and our responses to your specificLquestions (Enclosure 3).

You will note that one iteu - I etailed d control room review follow-up to IlPA-F008 -- recurs for nearly every plant li.sted in Enclosure 1. The control room design review process required

-licensees to identify all human engineering discrepancies that should be considered to enhance information flow to operators and then to assess which were significant and should be corrected. This has been an iterative process, but imple-mentation of control room improvements is well underway. The NRC staff has monitored this process and has concluded that all control room corrective actions needed to adequately protect the public health and safety have been completed. Actions remaining and scheduled for the future will further enhance the operator / system interface but are of lower priority relative to other actions being implemented at the plants. The extended Originated: NRR:Dudley 8906260014 890615 PDR COMMS NRCC I CORRESPONDENCE PDC j

schedules for these control room improvements also reflect time for proper engineering cesign, procurement of long lead-time equipment, implementation during planned refueling outages, and adequate improvements.

training of the operating staff with regard to the In the 10 years since the accident at Three Mile Island, licensees for the 112 reactors in the United States have implemented over 98 percent of the more than 10,000 TMI Action Plan items. These actions safety.

have contributed substantially to improving reactor The few remaining actions, such as completion of the control but room cesign reviews, will further enhance reactor safety are not needed to provide assurance that tne public health and safety are adequately protected.

In this same ten-year time period, the NRC moved effectively to improve reactor safety in other areas as well. Actions have been taken by the NRC staf f and reactor licensees to evaluate and resolve over 18,000 other generic and plant specific issues at individual reactor facilities. These other issues resulted from continual ef forts by the NRC staff, the nuclear industry and others coulo betoimproved.

identify situations in which plant design er op,eration The resolution of more than 28,000 potential safety issues in the decade following the Three Mile Island accident is, in my view, a record of accomplishment, not one of unwillingness or inability to fulfill our mission of protecting the public health and safety.

Although a small percentage of TMI Action Plan items has not yet been fully implemented, I remain conficent that the fRC staff and the nuclear industry have significantly improved the overall safety of commercial nuclear power operations. The neeo to accomplish this result was, ultimately, both the primary lesson learned from the TMI accident and the objective of the TMI Action Plan. I believe that we have met our post-TMI obligations to the public, ano I can assure you that we will continue to strive to serve the public interest.

I regret the time we have taken to provide a complete response to your March 23 letter and hope the revised information we are provioing items.

will clarify the current status of the Till Action Plan Sincerely, CV. /Ld b.

Lando W. Zeh,Jr.

Enclosures:

1. THI Action Plan Items to be implemented
2. Review Process and Criteria
3. Answers to Questions in March 23, 1989 letter

,~

4 ENCLOSURE I GUIDANCE FOR INTERPRETING ENCLOSURE I The following status abbreviations are used:

0 = unimplemented by licensee S = (for technical specifications only) submitted by licensee; currently under review and not yet issued i by NRC In most cases where scheduled implementation dates were not provided, the NRC staff has identified additional necessary corrective actions but has not yet formally notified the licensee. Thus, licensees were unable to provide imple-mentation schedules. These licensees will be requested to provide imple-mentation schedules when they are formally notified of the needed corrective actions.

I

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TLEETATim REVIEW REELTS FOR TMI ACTION PLAN ITDS IEEEr0737)

PLANT W K lERI TITLE /XSCR!PT!3 IPFLISTATim S00llED STATLE IPPLEETATIE DATE ARFANSAS 1 f H 071 DETA!!D GTR R02 REVIEW Falup TO TH008 0 ARKANSAS 2 01/31/91 T H 07!

DVERVEEY1 XTAILED CChTROL ROM REVD FOLLDE TO TH000 0 08/30/92 f H 971 EEAWR VEEY :

DETA! LED C2TR R REVIEW FOLLSE TO TH006 0 11!!0/89

.D. .:

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!<EAWRVALLEY2 PA-F071 05n1/29 3!BROCKF0!NT XTA! LED CONTROL R02 REV!EW FCLL0e TD TH0000 09/30/90

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W SFDS CONSCLE INSTALLD 0

BI6ROCKPOINT  !.D..: PLM SPDS CONSULI FlLLY IFLEETED 10/30/90 EIS Fs0CK POINT 0 10/30/90 f M 071 BPAIDWOOD 1 XTAILD CNTE R:Dt REVB Falue TO TH000 0 1.D.2.! 12/31/92 IRAIDWOOD 1 PLANT SPDS CWSEI RLLY 191 DENTED 0 f H 071 12/30/89 BRAIDl00D2 DETA! LED CNTE R00M REVIEW FE00 TO TH000 0

!.D.:.: 03/30/91 EAIDWD0D2 PLANT SPDS CMSaI FILLY IFLEETED 0 f H 071 03/30/90 XTAILD CONTROL R00M REV!EW FOLL0p TO TH000 0

BROWNS FEPSY 1  !.D..1 PLANT SPDS CWSaI DESCRIPTION 06/31/91 l R0W6 FERRY !  !.!.:.* P! ANT FDS CONSa.E INCTEED 0 12H1/12 l !ROPS FEPfY I  !.:.".! PLANT EDS CONSOLE FILLY IPLESTEI 0 1241/92 BF026 FERRY !  !!.E.2.0 O 12/31/92 PAS-PROCEMES 0

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! ACCIXNT MTORIECWTA19ENT PRESS if006 FIPSY ! 11.F.1.2.F 0 12H1/?2 ACCIDOU MTmlNG-CETAIN H2 iR086 FERRY 1 II.F.:.4 0 12/31/92

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I PLANT NIVE ISSLE TITLE!:ES3!PI!3 IFLESTAT!3 SCB1ID STATt5 LTLDENTATION

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IS CWERG BY SL 63-36 & 83-37 (UE6 0737) 0 f M 071 06/30/91 RNSWICK: P H 071 DETAILED 3TR1 R2 REVIEW FE0dP TD fM000 0 06/30/91 3RL*GW10r2 T H 071 XTAILED CDNTR1 irJ0M BIG FILDEF TO TH000 0 02/29/93 DETf,IifD C37R1 R2 BIEW FILudF TO TH000 EYRON1 T H 071 0 05/30/92 XTAILD CNTROL ROM BIEW FOLL0dp TO TH006 EYRON2 T H 071 0 01/31/80 XTA! LED 3'R1 R00M BIEW FOLL0dp TO THW ML E T CL;FFS : t H 083 0 09/30M CEET ES 1 'S ZEPED BY SL 63-36 L E3-37 (UEB 07371 0 {

t M 071 'J0/30/09 CALETCLIFFS2 T H 003 XTAILED ~NIROL R2 BIEW FIL0df TO TH0% 0 i

07/01/91 TS CDEPED BY GL B3-36 4 63-37 (UES 0737)

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f H 071 12/31/94 JC3EE 1 XTAILED C3TE ROM R' VIEW FEORF TO fM000 0 j

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FALD VEFCE : TH071 0 10/LB9 RLD EE ' XTAILED CONTE R00M REVIEh FOLLOWJ TO WWW0 /!

.0.2.7 8LANT EFDS CCNSOLE FEY IP.ESTD Ft0 M i TMP1 0 10!!0:29 XTArd C:h%. DOM FSV!EW FOLL:n T2 TH005 0 KACHP0TT2"  !.D..: PAT SPDS CONSULE INETEED 4ACH10%'M: 0 07/!1 9 LD. .3 W SFDS CCNSOLI FEY IRES ~ED DEACHPOTi?.2 D 07i!!!92 f M 072 E6 0737 T3 (COVERED BY SL 22-16 AND 53-02) 0

'EACH MTTOM 3 1.D.2.2 12/31/99 W SPDS CMS 0LI INSTALLED 4ACHPDTT:P3 0 10/30/B9

!.D.2.!

MT SPDS CONSEE FEY IPLEEN'ED 0 PEACHICTTe3 f M 072 06/30/91 KRRY1 E6 0737 TS (CMPID PY R 62-16 AND B3-02) 0 f M 071 12/31!29 PILSRIM ITAILID ATR ROT REVIEW FILDW.F TD fM000 0 01/30!91 1.D.2.3 W SPDS CONS 11 FEY !TLEENTED D 8!LSRIM T H 071 12/31/29 XTAllID CDNTROL R]QM PEVIEW FOLLMP TO THM 0 20!NT PEO 1  !.D.O.3 PLANT SFDS CONS 1E Fny !fLESTG 03/31/91 FOINT PE O 1 0 / /

f M 071 FOINTSEACH2 KTA! LED CONTF1 R30M BID FEDEF TO TH000 0 12/31/93 1.D.2.3 PLANT SPDS COMI FnY 19tEENTED POINTBE/CH2 f M 071 0 //

XTAILD C3CR ROGI REVIEW FILDEF TO FH006 0 12/31/93 PRAIRIE !SLAND 1 fM071 ETAllID CMTR1 ROM REVIEW FILDif TO FH000 0 12/31/96 89.A!RIE ISLAND 2 T&F071 ITA! LED CCNTR R031 PEVIEW FILMP TO TH000 0- 12/31/96

1 I

Paarno., 5 l

i

. :PIETAT13 REVIEh ESLLTS '

FM TM: ACT!$ PLM ITE5 t W H 7373 PLMT M :EEJE TITLE /ES21PT13 IfLEETATION SCD1E2 STATl5 IfLESTAT13 1

DATE '

l DUADCITIES1  !!J.:.4  !

7A) CITIES 1 9H071

[NST FT KirCT 7 IMD C71 C00Ll&lNSTE ADD'l INST 0 01/31/91 i

t DUADCITIES2 DETAllD CW1R1 ROOM REVIEW F1LDU TO TH0060 01/Mi?1 1

  • ! J.2. 4 INST FOR IETE" 7 IMD C0Ff C01!WINSTE ADD'l INST C

)

1UADCIT:EE2 S W O71 12/31/01 (

WCHO SECD XTAILED WP1 m EV!EW FDLLMF 20 THW 0 25G, '^

.f.:. A !NST FC#, ETE:! 'J MD CCFf C00JWINSTALL WL INST 0

FMCH) SECD  !!!.0.:.4.3 12!31lE9 C3l TROL F00M M5!TABILITY-ITtEST TDS 0

?ANCHOSE*0 '4f:'7! DETAILED CONTROL RDOM PIVIEW F0LLO& 70 TH006

%/%l25 ROEINSON 0 ll).2. .4.'c 041 % /'l CONTRCL E00M MBITABIL!iY-!TLEST CS 0 12/;1/90 ROBINSON TH13 IS CDED BY SL S!-36 4 83-37 (MS 0737)

ROBIM PH071 0 06/30/29 SG 1 XTAILED CCkTROL ROOM REVID FILDU 70 TH006 0 1.:.:.: DUWT SPDS C351E F1LY IPIOTED 12/31l91 1 ?ALEM1 0 03/% M 11.B.: 4 PAS-PLMT MODS (LL CAT B) l SALEM 1 1l F.2. 0 03/ 2 /90 INST FE DETECT 7 INAD CTE C011&SLSC00L G I SG ! T H E3 0 //

REM 1 TS CCNERED PY SL 8}36 4 SM7 (MG 0737)

PH%! TSC S 09/30/?'

SALEMi 0 TH071 10/ 2 /29

% TAILED C:h7R1 fd2 FIVIEW FULLCU 70 THX6 0 01/!!!'".

EALEM2  !.L.:.:

FA!IM2 PLANT SPDS C:NSE FILY IP.IETES 0 )

!!.i.:.4 PAS-ftANT EDS (LL CAT B) 03/01/c0 SG 2  ::J.:.: 0 03/% &

SALEM 2 !NST FOR DETECT 7 I've CZE C01!ESL~dC00L 'ETEF 0 //

Tei3 SALEM 2 TS CDVEFD BY GL SM6 4 53-37 (M5 07 7) S i

f H 063 TSC M/30.29 SG 2 TH071 0 10/30/89 IAN $0FFE 1 XTAILD CMTR1 R02 REVIEW FDL10U TD THW D 67.4.! R7 TRIP 03/31/91 5ANDNOFRE1  !.3.:. 0 09/ % /91 PLMT SFDS CCNSULE INSTEED SM ON7PI 1  !..:.! DLANT SPDS CONSULE FRLY IPleTED D 06/ % /93 0  :

SAN DGRE 1  !!.F. . 06/30/93 NST Fm DETECT T IMD CTE C00 LIE-ESC OTG EM DOTE :  !!.r.:4 0 12/01/29

NST FOR DETECT 7 INAD CORE C011GIGAL. ADL'l NT SAN ON0FE !  ::!.:.!.4.! CONTR1 MX]M MBlMBILITY-!5 TEST TDE D W/%/c!

FAN 04]FFI ! O 06/%d3 T W F!  :

XTAILEE '.:h7ROL ROOM iGIEW FULLCU TO THE00 SM O G RE 2  !.!.2. 06/30M3 itANT SPDS CONS 0LE FL11Y !TtESTD 0 SM DrJ5E : Pu" /i it4 CNyri ! ITAILE] CM FD FIV!EW FOLL3ff 70 to 002 .O :21:1!

2.:. _

TANT 5::S :350LE PALY :TLEsiD  : '

FAN ONTE : +HC!

'E200t'  :.;.:.: TAILED C%iROL EDOM REVIEW F0LLOU T0 +4+X8 0 07/31!':

PLANT SFDS C:NSULE F1LY IftE1YED 0 EABR00ri  ::1.A.2.1 02/15!91 PERADE PfEPMEMSS-iF9AI EESENCY FtMS TD O ENDII E 09/30/F 10CFR50 SEfM00k1  !!!.3.2.4.3 C3 fir (L R001 MBITABILITY-ITLEET TDS 0 SEQUD W 1  !.D.:. 09/30/E9 PLANT SPDS C:NSEE F1LY IFIETED SEQUDYM i f*-M3 0 07/31M UUDYM 1

~S CO G ED BY a 23-26 & B3-37 ( U ES 0737)

TH071 S 05/1!!?

EMYM 2 .2.!

DETAILED CXTR1 R001 PIVIEW FEDE TO FH006 0 10/!!!93

'LANT SPDS CDNSt11 FLLLY JTLEETED SEGUDYM 2 THE3 0 10/31M TS CODED BY SL EM6 i EM7 (UE5 07:7)

SEDLOYAH2 ~ fHU! S 05/31/29 SRIGAM 1.D.2.1 DETAILD C$iR1 RDOM REVIEW FOLLCU TO TH006 0 10/31/?!

PLANT SPDS C:NS1E ISCRIPTIS SSEHM 1.D.~.: 0 10/15/29 PUWT SPDS C3GU INSTUD SSEHM  !.D.2.: 0 08/31/80 PLANT SPDS CINSEI FlLLY ITLEDTD SUEHM THO*! 0 08/31/90 XTAILD CONTR1 R0m REVIEW FEDE TO FH000 0 08/11M l

Paoe Q . 6

- !HDENTATION REVIEW ERTS O TM! ACTION PUW ITEMS (UEB47373 P.MT WE l'.~xE I!iLE/XEZFTIJN IFLDENTATION SCOLLD STAT 15 IFLEBTATICH DATE

( ST LIIE 1 TA-F071 ETLiCIE2 T H 071 XTAILD CONTR M EVIEW FDLlurf 70 FH000 0 12/30/90 IJ901  !.D.2.3 ETA! LED C0hTR ROOM P! VIEW F1LDO TO TH000 0 12/30/90 SJSY1 PLMT SFS CONRE PHY !TLDGTED TH07! 0 09/30/90

?JSY 2 P M 071 XTA! LEE 03(TPOL Pn FEVIEW F1L0rf TD FHWD 12/31/94 WM T H 071 ETA! LED C1TR1 M EVIEW FDLLOU TO TH0000 12/31/94 TDPOE3 1.D.2.3 ETAILED CMTROL NOM SIEW FOLL0df TO WA0 8006 W/30/90 Pf> D POINT 3 8UWT SF:S CCNSCLE FEY IfLEHfD 0

!!.D.1.2.2 07/31/20 TD POINT 4  :.D.2.3 RELIEF & STETY VtVE TEST ED-PLMT SFECIFIC 0 EEPORT 07/31/90

( JeD POINT a PJWT SPDS C2S1E PHY ITLEMENTED 0

!!.D.1.2.9 07/31/09 6:10kT YMIE 1.D.2.2 RELIEF & SVETY VtVE ?EST EHLANT SPECIFIC 0 REPf.T 07/31/29 PLMT SPDS CONS 1E :NSTALLD (MNT YM11 1.D.2.! 0 10/31/90 4Pf0(T YWIE PUWT SFDS CONSE FEY ITLDENTED 0 T H 071 10/31/90 IJ6TLE 1 T H 071 DETAILD C3(TROL M EVIEW FILOWUP TO TH0000 10/31I90 GTLE 2 T H 071 MTA!!.D C3(IR R02 REVIEW F110dF TO FH000 0 10/31/90

  1. 2 TH071 EAllID C3 TROL P00M SIEW FDL10KF TO FH000 0 10/31/90

!!ON1 P H OB3 XTAILD C3(TR FIOM EVIEW FILDKP TO FH000 3 08/30/90 l131 T H 071 TS CDSED ?Y 1 BM4 & 93-!7 WK5 0737) 0 11/30/B9

N2 94-M3 DETAILD C3iTR R2 EVIEW FIL0dP TO TH000 0 0?/30/89

!!3 2 T H 071 15 C7EED BY R BM4 & E3-37 (UEB 0737) 0 11/30/29 XTAILD C3CR M EV:EW FULL 0dh TO FH000 0 05/02/90

\

ENCLOSURE 2 NRC REVIEW 0F THE STATUS OF TMI ACTION PLAN ITEMS By letter dated April 14, 1989, Dr. Thomas E. Murley, Director of the Office  ;

of Nuclear Reactor Regulation, requested that all licensees certify the current implementation status of all TMI Action Plan items. Projected implementation dates were requested for all items remaining to be implemented. 1 Licensees responded by indicating those applicable items that were implemented  !

and those that were not yet implemented. Infonnation received from licensees was compared with the NRC staff's records. If the licensee certifieo that actions were completed, the NRC accepted that certification after determining- '

that the staff's records or inspection efforts had developed no firm information to the contrary. In some cases there was a difference of opinion whether an l item had been implemented or was still open. For consistency, the staff used the definition that a TMI Action Plan item was considered to be implemented at  !

a plant if, based upon information regarding the completeness of licensee "

actions available as of May 19, 1989, the staff has decided that no NRC order or enforcement action would be appropriate.

After completion of the staff's review of the status of TMI action item imple-  !

l .mentati on, the current number of open issues was reduced to 254 from the 264 items I

that were previously listed as open in our letter'of March 17, 1989. A number of issues originally reported as closed are now considered open; similarly, some issues first reported as open are ncw considered closed. Many of the latter changes in status are due to implementation of items by licensees since February 1989, when the original status information was prepared. Our review of the status of TMI items also indicated that some modifications should be made to ensuriconsistency in the nomenclature by which the implementation of TMI-issues is tracked. Accordingly, a number of changes were made to the status of individual sub-items to ensure that these issues were all tracked consistently.

These changes, combined with other corrections made when our detailed review found certain data to be inaccurate, are the primary reason for the differences  :

between the status provided by our letter of March 17, 1989, and that provided in Enclosure 1 to this letter.

E______________------- - - - _ _ - - - - - - - - - --

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)

ENCLOSURE 3 1

j QUESTIONS AND ANSWERS CONCERNING IMPLEMENTATION OF THE TMI ACTION PLAN REQUIREMENTS-1 i

QUESTION 1 What priority does the NRC place on completing implementation of the TMI Action Plan Items?- Please explain how and why' reactors which have not met the TMI Action Plan requirements were

~

permitted to becin operation or, in the cases of Pilgrim:and -

Rancho Seco, to restart.

i l

ANSWER The NRC evaluates the priority of each TMI Action Plan item in conjunction with' all other NRC requirements, unique plant characteristics, interim measures, and i

the demonstrated licensee performance at each reactor facility. Similarly, the NRC authorizes a facility to restart or begin operation only after a careful review of the facility for compliance with NRC requirements and an evaluation of I

the licensee's demonstrated capabilities to safely operate the facility.

Occasionally, the NRC has authorized some licensees to begin operation of new plants or to resume operation of existing plants without full implementation of all TMI Action Plan items. In these cases, the NRC allowed operation only after

,3 ensuring that the licensee either had taken sufficient compensatory measures or had implemented the safety-significant portions of particular TMI Action Plan items so that public health and safety were assured.

i I

, .00ESTf0N.1 (Continued) - ~2 -

The TMI Action Plan items that were not fully implemented when the Pilgrim and the Rancho Seco facilities were authorized to restatt are discussed below.-

PILGRIM The NRC authorized the restart of .the Pilgrim facility in accordance with the approved Power Ascension Program (PAP). The PAP is a deliberate and controlled process that was expected to take 4 to 6 months and that is being extensively monitored by the NRC staff. The status of all open licensing items, including the remaining portions of the TMI Action Plan, were considered in the decision to restart Pilgrim. The status of the TMI items remaining to be implemented when Pilgrim restarted follows.

TMI Action Plan Item I.D.2.3, Safety Parameter Display System (SPDS)

All the SPDS equipment and hardware were installed and the initial tests com-pleted. The system software is being brought up to date to comply with the recently approved updates to the emergency operating procedures. The system will be tested and fully implemented by the end of 1989. In the interim, the-parameters needed by operators to control operation of the plant are available through previously installed indication systems.

Multiplant Action (MPA) - F071, Detailed Control Room Design Review (DCRDR)

Initial enhancements to the control room that resolved a nember of the human factors concerns identified by the licensee's DCRDR effort were implemented -

before restart of the facility. These enhancements included physical arrange-ment changes and installation of new work stations, a communications console, hardware replacements, and additional control board surface enhancements.

The licensee committed to accelerate implementation of other human engineering L____________-__-_________

, .0 VEST!0N 1 (Continued) .

improvements, specifically control board surface enhancements, which have already been identified, evaluated, and prioritized for implementation on the  !

basis of their safety significance.

The licensee's verification and validation of the new Pilgrim Emergency-Operating Procedures, which utilize the existing controls and instrumentation in the control room, did not identify any significant concerns. This con-4 clusion was confirmed by the NRC staff during its assessment of readiness for i the res+:rt of Pilgrim and also during a recent in-progress audit of the DCRDR .

implemr .ation effort.

l A supplemental summary report dated May 2, 1989, was recently provided by the l

1 licensee. This report provided an update of the licensee's plans to complete  !

the Pilgrim DCRDR effort and proposed implementation schedules for the remaining changes. The staff is reviewing the licensee's proposed plans and schedules I to ensure that tiley are consistent with the safety significance of the remaining modifications. '

i TMI Action Plan Item II.E.4.2, Containment Isolation Dependability Before Pilgrim restarted, TMI Action Plan items regarding containment isolation dependability were resolved except for part of sub-item II.E.4.2.7 - Radiation Signal on Purge Valves. At restart, sub-item II.E.4.2.7 was resolved for all containment isolation valves greater than two inches in diameter. The remaining issue involved isolation of small lines. The licensee has proposed minor procedure revisions to assure prompt isolation of these lines. The new proce-dures will be in place by the end of May 1989. Since no safety significant issues remain, the staff considers this item to be implemented by the licensee.

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QUEST 10N 4 (Continued) .

RANCHO SECO TMI Action Plan Item I . . A.2.2, Meteorological Data

. Meteorological program .'ficiencies that were required to be corrected before Rancho Seco could restart in 1988 are listed in.Section 4.4.1 of the Rancho Seco Restart Safety Evaluation Report (SER), NUREG-1286 (attached). The licensee corrected these deficiencies before restart, and the Rancho Seco meteorological capability was' adequate at restart to meet the TMI Action Plan requirement. The data in the NRC's tracking system has been updated to properly reflect this status.

TMI Action Plan Item III.D.3.4.3, Control Room Habitability All issues related to control room habitability were resolved before plant restart except for a concern that control room operators may be exposed to excessive radiation in the control room following an accident. Interim corrective actions that would protect control room operators from the poten-tially high radiation in the control room were implemented before restart. The interim remedies included the use of protective clothing, potassium iodide, and procedural requirements for radiation surveys. The licensee committed to further evaluate this issue and correct any design deficiencies with permanent modifications before restart after the next refueling outage (1989).

TMI Action Plan Item II.F.2.4, Inadeouate Core Coolino Instrumentation The licensee committed to implement this TMI Action Plan requirement by incorporating a reactor vessel level monitor before restart after the next refuelingoutage(1989). Section 4.6.2.2 of the Rancho Seco Restart SER,

, .0VESTf 0fbl (Continued) .

NUREG-1286, evaluated existing alternative methods available to Rancho Seco l operators to verify core cooling. The staff concluded that alternative  !

methods, in particular the Rancho Seco SPDS, are adequate interim methods to i monitor core cooling.

TMI Action Plan Item I.C.I.1, Emergency Operating Procedures On the basis of a review against criteria in the TMI Action Plan, Rancho Seco emergency operating procedures were found acceptable before plant restart in i

1988. The staff evaluation is included in Section 3.5 of the Rancho Seco l Restart SER, NUREG-1286, Supplement 1 (attached). Thus the staff considers this item to be implemented.

TMI Action Plan Item I.D.2.3, SPDS Fully Implemented Our letter of March 17, 1989, was incorrect in stating that the SPDS at Rancho Seco was not fully implemented. The SPDS at Rancho Seco was fully implemented 1

in accordance with the TMI Action Plan requirements before plant restart in 1988.

TMI Action Plan MPA - F071, Control Room Desien Review Implementation Control room modifications to resolve a number of human factors concerns were completed by the licensee before the facility restarted in March 1988. The licensee committed to complete the remaining control room modifications by refueling outage 9 (1991) per a design change package that has already been approved by the NRC staff. The staff has concluded that the licensee is making i

satisfactory progress toward full implementation of control room upgrades.

Because of '>,0 magnitude of the work involved, the staff has also found the l

proposed completion date of 1951 acceptable.

QUESTION 2 What is the NRC's system for monitoring and tracking the-implementation of TMI' Action Plan Items? How often are TMI Action Plan item requirements updated? Are resident inspectors required to ensure that deadlines are met? Have any penalties been assessed for failure to meet deadlines?

ANSWER I

L The NRC staff tracks the implementation of TMI Action Plan items and other safety issues with the Safety Issue Management System (SIMS). This system is designed 1 to record the date that licensee implementation is completed on such items.

Data on updated licensee implementation dates is obtained periodically by the I i

NRC Project Manager from meetings, site visits, or discussions with the resident inspector or the licensee. In the past, there has been no consistent procedure for updating the TMI Action Plan item requirements in SIMS. Once the

]

implementation dates confirmed by the staff's current review of the status of the TMI Action Plan items have been entered in SIMS, special SIMS updates will be performed on a quarterly basis.

NRC staff members at the regional offices and NRC resident inspectors ensure on a sampling basis that licensees meet commitments made to the NRC. Many of the TMI Action Plan Items were imposed by order or license condition. Those  !

covered by orders or license conditions can be enforced by sanctions in accordance with the NRC Enforcement Policy. For items covered by commitment rather than by specific order or license condition, if the licensee deviates from the commitment but remains in compliance with the Commission regulations, a notice of deviation may be issued.

]

1 OUESTION 2 (Continued) ,

l The decision to issue a deviation notice-is left.to the discretion of the I inspector and his management and depends primarily upon the safety signifi-cance of the issue. Generally, deviation notices are not issued to licensees for minor schedular delays that have an insignificant impact on safety. If the deviation persisted and the' matter was of sufficient safety significance. ' the.

staff would consider issuing an order to ensure resolution of the issue. 'NRC  !

inspectors continue to ' track deviations to ensure that they are satisfactorily resolved by licensees. j 1

i Whenever safety-significant violations occur, the NRC staff initiates. escalated I

{

enforcement and proposes civil penalties in accordance with the NRC enforcement

{

policy described in 10 CFR Part 2, Appendix C. As we discussed'in our letter of March 17, 1989, the NRC has cited licensees for eight violations and '

two deviations associated with TMI Action Plan issues. Escalated enforcement for one of the violations resulted in a civil penalty of $50,000 that was levied 1 on the licensee of Palo Verde, Unit 1, for failure to properly implement the Post-Accident Sampling System (TMI Action Plan Item II.B.3) before operating the reactor above the 5-percent power level.

i i

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_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ 2

d

. j OUESTION 3 Of the 88 licensed reactor:; which have not completed implementa-tion of all TMI Action Plan items, how many extensions of deadlines were given? What was the length of these extensions? q ANSWER I I

i The publication of implementation schedules proposed by NRC in NUREG-0737 and  ;

earlier TMI-related documents (NUREG-0578 and NUREG-0660) did not impose these dates as legally binding obligations on licensees. After receiving licensees' responses to the NUREG requests, many of the TMI items, including licensee proposed plant-specific implementation schedules, were mandated by confirmatory '

orders or by license conditions. In a number of cases. -these oraers or license j conditions were modified by the NRC to extend licensee implementation schedules l for good cause shown by licensees. In such cases, these delays were often shown j to result in better integration of related reviews or were found acceptable ' '

because of compensatory measures that were implemented by the licensees.

i As previously discussed in the response to Question 2, the Safety Issue Management System is designed to record the date that licensee. implementation is completed for TMI Action Plan items and other safety issues. The NRC did not develop a tracking system dedicated to recording the number of schedular I extensions authorized for TMI items and the corresponding lengths of these extensions. Therefore, the NRC staff is unable to provide a detailed listing of schedular extensions and their durations for TMI Action Plan items.

9

4a V l

QUESTION 4 By the NRC's own. admission, the deadline for TMI Action Plan I

requirements at 23 reactors passed without the NRC receiving q

confirmation of implementation.- Please explain why the NRC was not informed of the status of these requirements. What were the i dates of these deadiines? I i

l ANSWER j

l l

NRC regulations do not require licensees to report to the NRC whenever they l 1

complete implementation of TMI Action Plan items or other NRC requirements. 1 Data on licensee implementation dates is entered into the SIMS by the NRC j Project Manager. The Project Manager periodically obtains updated information jl l

on implementation dates by the methods oiscussed in the response to Question 2.

1 The implementation dates in our Varch 17, 1989 letter vere listed as "NONE" i whenever licensees had not provided implementation schedules or whenever the licensee's previously estimated implementation date recorded in SIMS had passed and the Project Manager had not yet confirmed that installation had been completed. During the recent review of the status of TMI Action Plan items, the staff confirmed that licensees have implemented 18 of the 28 items listed as "NONE" in our previous letter. Updated projected implementation j dates have been provided by licensees for the 10 remaining cases for which l previously estimated schedules had elapsed or for which implementation aedules l

had not been provided. For these 10 issues, the previous and the current implementation schedules are shown in Table 1. The NRC staff has reviewed the  ;

new schedules listed in Table 1 and has found them' acceptable. They are consistent with the safety significance of the issues and none of the new dates violates a deadline established by NRC regulation, order, or license condition.

l

OUESTION 4 (Continued) TABLE ~1 - IMPLEMENTATION SCHEDULE Previous' Current Issue Implementation Implementation Plant No. Title Schedule Schedule Browns Ferry 2 II.B.3.3 PAS - Procedures none 06/30/91 Crystal River 3 III.D.3.4.3 Control Room 00/89* 03/30/90 Habitability -

Modifications Oconee 1 III.D.3.4.3 Control Room 12/88 09/30/89 Habitability -

Modifications Oconee 2 III.D.3.4.3 Control Room 12/88 09/30/89 Habitability -

Modifications Oconee 3 III.D.3.4.3 Control Room ~1 2/88 '09/30/89 Habitability -

Modifications.

Oyster Creek MPA-F071 Detailed Control Room 12/88 10/31/90 Design Follow-up Surry 1 MPA-F071 Detailed Control Room none 12/31/94 Design Follow-up Surry 2 MPA-F071 Detailed Control Room none 12/31/94 Design Follow-up Zion 1 MPA-F071 Detailed Control Room 00/88* 09/30/89 Design Follow-up Zion 2 MPA-B083 TS Covered by GL 83-36 00/88* 11/30/89 and 83-37

'l 0

This indicates the action was scheduled to be implemented sometime during the indicated calendar year.

I

l 1

a QUESTION 5 In NUREG-1355, "The Status of Recommendations of the President's Commission on the Accident at TMI," the NRC states that "a i

Safety Parameter Display System has been installed in all nuclear power plant control rooms, except for three systems i

scheduled for installation and one licensee granted an authorized exemption." Please explain why, in the information provided to me by the NRC, there are 23 reactors listed which have not completed installation of such a system. Please also i

explain why in your 3/17/89 response to me you did not include j

this " authorized exemption" in the list of plants given exemptions from the Action Plan. Are there additional i 4

exemptions which were not included?

1 1

ANSWER.

I i

The recent staff review of TMI Action Plan implementation information received l from licensees has 7nabled the NRC to resolve previous discrepancies regarding the implementation status of Safety Parameter Display Systems (SPDS). Nine reactor units have not begun installation of their final SPDS equipment to conform to the standards established in NUREG 0737, Supplement 1. An addf-tional 31 have installed the SPDS but must make additional improvements to the equip-ment or software in order to meet the staff's design criteria specified in NUREG-0737, Supplement 1.

f

s

'b OUESTION 5 (Continued)  ;

b

(

The primary reason for the inaccuracies in the 'NUREG-1355 statements and the information provided by our letter of March 17, 1989, is that the NRC did not previously utilize uniform definitions for the terms " installed" or "imple:-

mented." Many plants are now in the process of installing Safety Parameter 1 Display Systems and therefore have not yet undergone final NRC review. Addi-l tionally, other plants installed interim SPDS systems before the NRC established specific SPDS design and interface criteria in December 1982.. The NRC staff and )

these licensees are reevaluating the interim SPDS systems to upgrade them as necessary to meet the NRC's technical positions. Because of previous inconsist--

ent use of terminology, NUREG-1355 and the information in our March 17, 1989 letter referred in a number of instances to interim and partially completed SPDS i installations as " installed" or " implemented."

In order to complete our SPDS evaluations, the NRC staff has developed a program over the last year to certify the status of SPDS at all licensed facilities.

A generic letter was recently issued on April 12, 1989, requesting licensees to '

provide one of the following:

1. Certification that the SPDS fully meets the requirements of NUREG-0737, Supplement 1.

i

2. Certification that the SPDS will be modified to fully meet the require-ments of NUREG-0737, Supplement 1.

O OUESTION E (Continued) 3. If a certification cannot be provided, a discussion of the reasons for that finding and a discussion of the compensatory action the licensee intends to take or has taken.

No licensees have received authorization from the NRC that would permit them not to install an SPDS. Thus, the statement in NUREG-1355 is not correct regarding "one licensee granted an authorized exemption."

The NRC staff is not aware of any additional TMI Action Plan exemptions that were not already described to you in our letter of March 17, 1989.

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