ML20147F572

Summary of 970306 Meeting W/Nneco in Rockville,Md Re Licensing Activities at Facility.List of Attendees Encl

ML20147F572
Person / Time
Site:	Millstone
Issue date:	03/21/1997
From:	Mcdonald D NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9703260206
Download: ML20147F572 (14)

Text

60$b y y$

p

• UNITED STATES NUCLEAR REGULATORY COMMIS810N Jo ,

WASHINGTON, D.C. SegeHoot March 21, 1997 LICENSEE: Northeast Nuclear Energy Company (NNECO)

FACILITY: Millstone Nuclear Power Station, Unit No. 2

SUBJECT:

MEETING SumiARY REGARDING THE MARCH 6,1997. MEETING HELD TO DISCUSS LICENSING ACTIVITIES - NILLSTONE WUCLEAR POWER STATION, UNIT NO. 2 PURPOSE The meeting was convened to provide representatives of NNECO an opportunity to discuss with members of the Nuclear Regulatory Commission's (NRC) Special Projects Office its licensing process, ongoing improvements, current activities and issues.

The meeting was held in the NRC One White Flint North Office (originally scheduled for.Two White Flint) in Rockville, Maryland. A list of attendees is attached as Enclosure I and the reference material provided by NNECO is attached as Enclosure 2.

SUMMARY

An overview of the organizational structure of the Nuclear Licensing Services was provided which included details of the responsibilities and interactions of the licensing staff with the technical support staff, operations and safety committees' as they relate to regulatory issues involving correspondence and interactions with the NRC. The flow chart in Enclosure 3 for a proposed Technical Specification change request was used as an example of the current process. NNECO indicated that they had done a self-assessment and determined that improvements were needed to enhance the quality, accuracy and timeliness of. correspondence to the NRC. The steps being taken include placing increased emphases on the verification of the quality and accuracy at every step in the process, regardless of the schedule, written notification of schedular changes, and that Nuclear licensing will accept ownership and accountability for the final products. In addition, as an interim independent verification of the quality of amendment requests, Virginia Electric Power Company will be included in the review process.

Licensing issues were discussed including the actions which have already been submitted to the NRC and those that NNECO is currently aware of that n'eed action by the NRC staff prior to the start up of Unit No. 2. A listing of the required actions is included in Enclosure 4. Items number I and 6 of Enclosure 4 have been submitted, however, significant changes and corrections by NNECO are required in order for the NRC to complete its review. The NRC staff emphasized that its timely review of the requested actions is dependent on the accuracy and quality of the information provided by NNECO.

me rucommcon cm1'

g 2gggg gggg3, p PDR

l fiarch 21, 1997 The meeting was informative and provided the NRC staff general insights of NNECO's process for handling regulatory issues and the actions it is taking to improve the overall efficiency and effectiveness of its process.

Original signed by:

Daniel G. Mcdonald Jr., Senior Project Manager Special Projects Office - Licensing Office of Nuclear Reactor Regulation ,

6 Docket No. 50-336

Enclosures:

As stated cc w/encls: See next page HARD COPY

'r Docket 'Filel PUBLIC SP0 Memo OGC '

ACRS E-MAIL .

SCollins/FMiraglia RZimmerman WTravers i PMcKee 4 4 t'DMcDonald

'LBerry , 1 i

• EJordan (JKR)' '

WDean (WMD)

DOCUMENT NAME: G:\ MCDONALD \MTG. SUM Ta recdve a copy of tido document, Indicate in the box: 'C' = Copy without ottachment/pcMure *E" = copy with attachment / enclosure

'N" = No copy 0FFICE SPO-L:PM r l 5 ,SP,0-L : LAn O l SPOIMPL/ l l l NAME DMcDonal H M )>' LBerry 7

~

PMhYhe' L DATE 03/p(/97 03/dt/97 07/1)/97 0FFICIAL RECORD COPY

/

2G0051 l

-)

. . . . _ . _ _ ~ .. - - . _ _ . _ _ _ _ . _ . _

e 1

1 s i F

The meeting was informative and provided the NRC staff general insights of  ;

NNECO's process fnr handling regulatory issues and the actions it is taking to improve the overall efficiency and effectiveness of its ocess.  !

i Daniel G. Mcdonald Jr., Senior Project a ager Special Projects Office - Licensing Office of Nuclear Reactor Regulation Docket No. 50-336

Enclosures:

1. List of Attendees

(' 2. Reference Material

-3. Flow Chart

4. List of Required Actions a

i, cc w/encis: See next page I

1 l

f 4

d i

9

-. . . - - ,. _ _ . . . - - =. .-

Northeast Nuclear Energy Company Millstone Nuclear Power Station i

Unit 2 ,

cc:

Mr. F. C. Rothen Lillian M. Cuoco, Esquire Vice President - Nuclear Work Services Senior Nuclear Counsel Northeast Nuclear Energy Company Northeast Utilities Service Company P. O. Box 128 P. O. Box 270 Waterford, CT 06385 Hartford, CT 06141-0270  :

Ernest C. Hadley, Esquire 1 Mr. John Buckingham 1040 B Main Street Department of Public Utility Control P.O. Box 549 Electric Unit West Wareham, MA 02576 10 Liberty Square New Britain, CT 06051 Mr. D. M. Goebel Vice President - Nuclear Oversight Mr. Kevin T. A. McCarthy, Director Northeast Nuclear Energy Company Monitoring and Radiation Division P. O. Box 128 i

Department of Environmental Protection Waterford, CT 06385 79 Elm Street l 1

Hartford, CT 06106-5127 Mr. M. L. Bowling, Jr. i Millstone Unit No. 2 Nuclear i Regional Administrator, Region I Recovery Officer  !

U.S. Nuclear Regulatory Commission Northeast Nuclear Energy Company 475 Allendale Road P. O. Box 128 King of Prussia, PA 19406 Waterford, CT 06385 )

First Selectmen Mr. J. K. Thayer Town of Waterford Recovery Officer - Nuclear Engineering Hall of Records and Support 200 Boston Post Road Northeast Nuclear Energy Company Waterfoid, CT 06385 P. O. Box 128 Waterford, CT 06385 Mr. Wayne D. Lanning Deputy Director of Inspections Deborah Katz, President I Special Projects Office Citizens Awareness Network '

475 Allendale Road P. O. Box 83 King of Prussia, PA 19406-1415 Shelburne Falls, MA 03170 Charles Brinkman, Manager Mr. B. D. Kenyon Washington Nuclear Operations President and Chief ABB Combustion Engineering Executive Officer i 12300 Twinbrook Pkwy, Suite 330 Northeast Nuclear Energy Company i Rockville, MD 20852 P. O. Box 128 Waterford, Connecticut 06385 Senior Resident Inspector Millstone Nuclear Power Station c/o U.S. Nuclear Power Station I P.O. Box 513 l Niantic, CT 06357 i

Citizens Regulatory Commission ATTN: Ms. Susan Perry Luxton '

180 Great Neck Road Waterford, Connecticut 06385 l

Mr. Allan Johanson, Assistant Director Office of Policy and Management

Policy Development and Planning

• Division 450 Capitol Avenue - MS# 52ERN P. O. Box 341441 Hartford, CT 06134-1441 Mr. Neil S. Carns i Senior Vice President I and Chief Nuclear Officer Northeast Nuclear Energy Company c/o Mr. Richard T. Laudenat Director - Regulatory Affairs i P.O. Box 128 i Waterford, CT 06385 l l

l

1 ATTENDANCE LIST '

March 6. 1997  ;

NORTHEAST UTILITIES / NUCLEAR REGULATORY COMMISSION j

. 1 HARE ORGANIZATION Daniel Mcdonald NRC/SP0-L Ravi Joshi NU/ Millstone 2 Licensing Harry Miller NU/ Millstone 2 M. L. Bowling NU/ Millstone 2 Recovery Officer Phil McKee NRC/SP0 i

_ . _ . . . _._ _ . _ . _ _ ~ _ _ _ . _ . .

i  :

i 1

4 1

! l l NU/NRC MEETING Millstone Unit No. 2 i

i l

Purpose:

To Discuss the Licensing Activities for Millstone 2

] I l Location: 2 White Flint, Conference Room -T3-C-1 j

! 1 i' Date and Time: March 6,1997 - 10 a.m. to 12 noon

! AGENDA i

1

e Current Licensing Process for Outgoing Letters, Technical Specification Changes, j and Reportability Requirements j e Plans for improving Quality and Timeliness of the License Amendment Submittals e ' Discussion on Licensing issues License Amendments Relief Requests l- - Exemption Requests )

j -

Other Licensing issues  :

i l; e Summary i I

I l

l 1

1 Enclosure 2

OUTGOING CORRESPONDENCE OUTLINE l -

NRC lasues letter requiring response NNECO receives letter a-Action Assignments made in AITTS Letter is distributed internally i-Lead Functional Manager assign an individual to develop NRC submittal Lead Functional Manager consolidates input from other Functional Managers j and submits to Nuclear Licensing i

l Nuclear Licensing drafts the formal response for submittal to the NRC Nuclear Licensing distributes the draft submittal to the Functional Managers for i review and signoff Officer signs the submittal i Nuclear Licensing inputs commitments made in the letter into AITTS

)

1

$ 1

l 1

I i

i i

I . . .

j i . i i

k i

j 2-

FIGURE 7.1. FLOWCHART PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUESTS l

, 1 I. ORIGtNATOR

• I1

• m Obtain opptov ofim te Supervisor.

7

, 4 Identty effected FSAR Sectons.

From7.12 op PTSCR Record FSARCR # and Attach FSARCR, if spoheeble t

._pjuppg, _ MANAGER ENGINEERING SYSTEMS

Review PTSCR. Approve / Disapprove.

1 UNIT OPERATIONS MANAGER sappmW - ReviewPTSCR. ApproveOsepprove.

i -

Y MANAGER.NL Log in, assign serief number, and l assign review completion dates.

, Venfy effect on FSAR, and assign FSARCR W.

Designate Technice! Reviewers i TECHNICAL REVIEWERS

! Determine Safety of the Change.

Make SHC Determmation Venty effect on FSAR, and review FSARCR if apphceble.

T i 1

MANAGER RADIOLOG! CAL ASSESSMENT l Determine anyincrease in I individus! or cumuistive re$stion exposure or in effluent releases Y

MANAGER-SAFE 1Y ANALYSIS Review Safety and SHC Determinston. j dr Y

MANAGER NL MANAGER GENERATION AND + Determine need and perform en Environmental l ENVIRONMENTAL LICENSING Assessment,if required. i Assist preparaton of Environmental Assessmentif required

-> Review PTSCR and update log Prepare anal SHC Determination and Sa'ety Assessment

• l

.A1 e4m Cont.7.12 of 2 l

1 Rev.10 m.somoe NGP 4.02 Page 7.11 of 2  ;

E m l e rrrd B

l

, F10URE 7.1 - FLOWCHART PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUESTS (CONT.)

A1 From 7.1 1 of 2 Y

PDRG/50RG Review and recommend approvavesapproval of TSCR and/or i Bases Change UNIT DIRECTORMCE PREstDENT-NUCLEAR OPERATIONS Review and approveldsepprove PTSCR.

1 Bases MANAGER-NL Update log and review for completeness. D$ approved 31 Changes Prepare submras! letter to NRC. > To7,11 of 2 Forward PTSCR and letter to NSAB Secretow I

. NSAB-SE l Resew PTSCR i Recommend approval /esapprovst of PTSCR.

NSAB

! Revsw and approvelesapprove PTSCR Dsapproved )

and correspondence to NRC l

. 2 NSAB. MANAGER-NL. UNIT l DIRECTORMCE PRESIDENT NUCLEAR Dsepproved[ -B1-OPERATIONS. EXECUTIVE VICE >

PRESIDENT / CHIEF NUCLEAR OFFICER Q7.11 of 2

! Ag ee on approvellesapproval a m V

l MANAGER NL U Depoorbon PTSCR and/or Bases Changes i U Implement DC 10 and/or

. ADM 1.1258.

4

)

es s nur

. Rev.10

age.sc.use NGP 4 02 Pope 7.12 of 2

i 4

i PLANS FOR IMPROVING QUALITY AND TIMELINESS OF THE

. LICENSE AMENDMENT SUBMITTALS i i

Millstone 2 Licensing will take ownership of license amendment submittals Quality and accuracy will be verified at every step of the process ,

I a

i -

Schedule is important but submittals will not be rushed through to meet  !

] deadlines 1

Change to commitment date will be officially notified to the NRC Add Virginia Power on review of License Amendment Requests i

e t

s i

d I

l l

I i

i

! DISCUSSION OF LICENSING ISSUES i*

i

• License Amendments l e Relief Requests l

None identified at this time

• Exemption Requests

- None identified at this time

. Other Licensing issues GL 96-01 (Overlap Testing)

GL 96-06 (Containment integrity During Design Basis Accident Conditions)

GL 87-02 (A 46)(Seismic Outlier)

Large Break LOCA Analysis l

. Licensing issues that may require Technical Meetings with the Staff i

- Startup-Rate -Trip  !

R.G.1.97 o Core Exit Thermalcouples - Power Supply Requirements

- Auxiliary Building Ventilation a MCC B51/B61 o EQ issues Appendix 'R' 4

REQUIRED LICENSE AMENDMENTS FOR MP2 STARTUP s/m7 NRC No. TAC No. 189 Stan TS/ OPS SA/SHC All slanet RQBG g&&R ggg 1 MG4105 11 Descriotion TNs PTSCR rnodifes apphcabdity and actens assocated with Steam Generator Blowdown Mondor. Modifes apphcabdity for I Condensate PohsNng FacHity Weste Neut Sump NRC No. TAC No. 119 Q038 TS/ OPS galliiG All Sinned EQBG Hi&B M82 2 M97746 25 2/14S7 2/18/97 2/28/97 3/7/97 3/12/97 3/21/97 3/25/97 Description TNs PTSCR (2-5 97) supersodes PTSCR 2197. P proposes to rnodify the minimum matrument accuracy m Table 3 3-8 for the Met Tower instrumentaten NRC No. TAC No. 119 Qta$ TS/ OPS SA/SHC AllSioned EQEg Ngag Nag 3 M97741 2ts Description TNs PTSCR provides changes regarding the organgstenal structure and titles.

_ _ _ . ~ _ . ._._ .

NRC No. TAC No. 119 Qtan TSIOPS SA/SHC AH Signed gQBq gjag ggg 4 14 1/24/97 1/29/97 2/21/97 2/28/97 3/10/97 3/17/97 3/31/97 Qgacription This change wHl ehminate the reference to the measurement locaten for the Ulbmate Heat Sink in TS 3 7.11 An NRC committment j per LER B16115 exists to submitted the PTSCR by 3/31/97.

NRC No. TAC No. 119 Qtan TSIOPS SA/SHC All Sinned 2QBQ N$AS NEG 5 15 1/31/97 2/7/97 2/21/97 3/7/97 3/14/97 3/21/97 3/31/97 Description This PTSCR would ehminate the requrement to enter LCO 3 0.3 when the enclosure building is breached. due to making both trains of the enclosure building ventaston system enoperab6e (unable to create vacuum within specifed trne pered)

NRC No. TAC No. 139 Qtan TSIOPS SAISHC AllSiened PORC NEAR NgG 6 M94623 16 2/28/97 3/7/97 3/1497 3/18/97 3/21/97 3/31/97 Description TNs FTSCR redefines containment integnty to permit operator acten dunng permos when containment notaten valves may be opened under admin controls Also relocates the hst of containment notaten valves from TS to the TRM The current PTSCR needs to be modsfed to add a descussen of administratrve controls to the bases.

NRC No. TAC No. 189 Qtan TS/ OPS SA/SHC AllSioned EQBG NSAB NRG l 7 18 3/7/97 3/12/97 3/20/97 3/28/97 4/7/97 4/14/97 4/21/97  ;

Description j TNs PTSCR modifes the bases to resolve the EDG fuel ou storage capacity osue NRC No. TAC No. 119 Qian TS/ OPS SA!$MC All Sianed PORC NEAR NEG 8 67 2/28/97 3/7/97 3/14/97 3/21/97 3/21/97 4/7/97 4/14/97 Description Need to add 2 second time delay to ESFAS Table 3 3 4 8a to be consstent with 8b and ITS Page 1 of 2 Enclosure 4

y _

REQUIRED LICENSE AMENDMENTS FOR MP2 STARTUP s/3/e7 NRC No. TAC No. 119 Sta$ I&!QP,.1 SNSHC AllSioned EQRQ $$ag NRG 9 1 3/1497 3/20/97 3/2697 N N97 N 9S7 N1tV97 4/30/97 Dancription The PTSCR deistes TS 3/4 9.14 and Tatde 3.9-1. rnodires LCO 3.9.15 to require two EBFS trains to be operetne and adds the foquirement to have at least one train in operatson whenever fuel movement or crane operaten e in progress, ados a requirement regarding spent fuel pool area ventilation integrity, changes the assocated actens requirements, changes the surveillance requirements, and the bases This change removes the requirement for the " blue lights" and will not requere gorng mto AEAS pror to fuel movement.

NRC No. TAC No. I19 gra!! 11.5221 SNSHC AH Sioned 29RG lG&S jgG 10 68 3/7/97 3/1N97 3/21/97 3/28/97 4/ 7/97 N21/97 4/30/97 Descristen TS 3 41.3 Action could require Mode 5 with no SDC loops operstne.

NRC No. TAC No. 11.9 QtAR TSIOPS SA/SHC AllSianed EQEQ NSAB ggG 11 M92879 12 Descriotion This PTSCR revises several surveillance requirements regarding Control Room Emergency Ventuaton System l

NRC No. TAC No. 11.9 Qtat! TSIOPS SNSHC Att Sianed EQEQ Mt.A,3 jgG )

12 73 3/14/97 3/20/97 3/28/97 4/4/97 4/11/97 4/18/97 4/3097 Description l

Amend.151 removed wording that 3.0 4 is not applicat8e from the PZR PORV TS '

NRC No. TAC No. Igg pyraft TSOPS SNSHC AllSinned EQEQ !G.83 NEQ 13 75 3/1

• 97 3'21/97 3/2BS7 4/497 4/11/97 4/18/97 4/30/97 ggastlotion Note m COLR modifes the DNB LCO This PTSCR wel add the note and the DNB parameters to the TS NRC No. TAC No. I1g Stift TS/ OPS SNSHC AH Sinned NE&B EQB.Q NEQ 14 82 3/15/97 3/21/97 3/28S7 4/4/97 4/11/97 4/18/97 4/30/97 Description Heactor inp setpoints for SG safety valves in Table 3 71 based on 107% power mstead of 106 6%, so nonconservative NRC No. TAC No. 119 gra!! TSOPS $NSHC AlfSinned EQRQ !G&g jgG 15 104 3/14G7 3/20/97 3/27/97 4/4/97 4/11/97 N18/97 N30/97 Description Errors in the RCS Pressure /7emperature Curves May require a change to the Tech Spec P.T cunes 16 TOTALISSUES Page 2 of 2 O