ML20213E474

From kanterella
Jump to navigation Jump to search
Requests Input to SER Suppl 4 by 830815.Marked-up Copy of SER Suppl 3,Sections 1.7,1.8 & 1.9,listing Status of All Open & Confirmatory Items,Encl
ML20213E474
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 07/22/1983
From: Rajender Auluck
Office of Nuclear Reactor Regulation
To: Schwencer A
Office of Nuclear Reactor Regulation
References
CON-WNP-0603, CON-WNP-603 NUDOCS 8308010066
Download: ML20213E474 (6)


Text

'

+

~

Jul. 2 2 1983 DISTRIBUTION: _ .

EHylton RAuluck f!E!!0RANDUf1 FOR: Distribution List (attached)

THRU: A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing FR0ft: R. Auluck, Project flanager Licensing Branch No. 2 Division of Licensing

SUBJECT:

WNP-2 OPERATIrlG LICENSE REVIEW The current schedule for the issuance of operating license for WNP-2 is September 1983. At present, SSER #4 is scheduled for late August 1983.

Your input for this supplement is requested by August 15, 1983.

Attached is a markup copy of SSER #3, Sections 1.7,1.8 and 1.9. These sections list the current status of all the open and confirmatory items and a lso the proposed licensing conditions. Please review these carefully for any additionisor deletions and prw ide the current status of your review by July 2 9,1983. The licensee has agreed to provide all the information requested by the staff to resolve the existing issues by August 1,1983.

l Please call Raj Auluck (28457) if you desire more information.

Q:iglan'. c!3n;d b7:

R. Auluck, Project Manager Licensing Branch No. 2 Division of Licensing

Attachment:

As stated l

l l

8308010066 830722 i W ADOCK 05000397 sf:-

.u DL:LB#2/PM DL1LB#2/BC l CFFICE) . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . .. . . . .........a .... . . . . " . * * . . . " ... " ." a ~ -

SURNAME) .h. . ,d.h.. ,, .. , , h0.h,e r,,, , , , , , , , , , , , , , , , , , , ,, , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , _ , _ , . . , ,

7/ u/83 04rE ) 7../.W........ 8 3 .. . ... . .. . . . .. .. . . . . . . . . . . . . . . . . .... . . . ~ . ....... - - - -

-l-pc reau ats co coi sacu eaa OFFlClAL RECORD COPY uwoom-m-m

. .DISTRIBUTXON LXST:

T. M. Novak R. Li ,

J.

  • Knight K. Leu W. V. Johnston 6. Gupta D. Muller J. Kimball W. Houston I'. Al terman L. Rubenstein A. Masciantonio H. Thompson J. Jackson E. L. Jordan R. Wright J. M. Taylor M. Hum R. Bosnak J. Schiffgens G. Lear D. Smith R. Jackson D. Kubicki V. Noonan F. Witt B. Liaw G. Staley V. Senaraya T. Collins R. Ballard R. Kendall W. Regan F. Eltawila B. Sheron J. Ridgely F. Rosa S. Rhow W. Butler R. Giardina
0. Parr M. Tokar M. Srinivasan W. Brooks C. Berlinger S. Sun I

L. Hulman F. Akstulewicz W. Gammill J. Levine F. Congel C. Miller V. Moore C. Hinson D. Beckham J. Nehemias

H. Booher R. Froelich H. Clayton F. Allenspach F. Pagano R. Urban i G. Ankrum M. Gaitanis J. Gilray s

Item Status Section(s)

(18) Blockage of the.DG combustion air Resolved intake and exhaust system 9.5.8 (19) Shift support supervisor training program Resolved --

(20) Administrative procedures:

Resolved --

limitation on working hours (21) Criteria for testing hot pipe Resolved --

containment penetrations (22) Emergency planning program (offsite)

O' *M ~

g '"-+*er --

irf:r :tian (23) Control room design review Under review --

(24) Anticipated transients without scram Combined with --

(ATWS) confirmatory item 15 (25) General Design Criterion (GOC) 51 _ Resolved --

';) TMI II.E.4.2 (operability cf purge Under. review --

valves only) ,

TMI II.K.3.28, qualification of Resolved --

accumulators on automatic depressurization system (ADS) valves (28) Pipe break in the boiling water Resolved 4.6 reactor C8WR) scram system

~~~~

(29) Steam bypass from a stuck open Awaiting further --

wetwell-to-drywell vacuum breaker information (30) Heavy load handling system Under review --

(31) Sprinkler and st'andpipe system Resolved 9.5.1 (32) Organizational changes . Resolved 13.1.1 (33) Cable separation criteria Resolved --

1. 8 Confirmatorv Issues In Section 1.8 of the SER, SSER 1, and SSER 2, the NRC staff listed confirmatory items that were not resolved at the time of issuance of those documents. That -

list is reproduced and updated below.

%s

u. ,

ods%Q

- b low,.with the rrent statu of each item For it ms dis ussed in th(s sp-pie ent, the spec 1 ic section i identified. The res ution f th rema1Nihg outs nding items wi 1 be discuss in future pplemen.s to t e SER.

Item Status Section(s)

(1) Geology and seismology Resolved --

(2) Internally generated missiles Resolved 3.5.1 (3) Tornado missile protection for . Resolved 3.5.2

~

diesel generator (DG) exhaust ResMvd (4) Turbine missiles N:'t "; 'rthcc --

~

i '-- 2'=cn (5) Component supports Resolved (6) Equipment qualification Awaiting further 3.10, 3.11 information (7) Condensation oscillation and chugging Resolved load specifications

~ ~

(8) Pressure interlocks on emergency core Resolved --

cooling injection valves

. 9 e.s h e O (9) Modification of automatic E:# t; #

' rth:- --

depressurization system logic 4 # e "-" Mn (10) Standby service water, system Resolved 7.3.2.4 instrumentation and control (I&C) design (11)-Engineered safety feature reset Resolved --

control --

(12) Remote shutdown system I&C design Resolved --

(13) Control system failures

@ Aa.vWo N:it "; ' r*2er --

, ir' rmat hn

.(14) Adequacy of station electric Resolved --

distribution system .

~

(15) Quality group classification for the Resolved --

DG auxiliary systems (16) Diesel engine cooling heater preheat Resolved --

(17) Diesel engine lube oil system's ability Resolved --

to preclude dry star. ting WNP-2 SSER 3 1- 2 -  :

Item Status Section (1) Break location Awaiting further --

information (2) Preoperational testing of snubbers Under review --

(3) Reactor internals analysis under faulted Under review --

conditions .

(4) Hydrodynamic loads '

Under review J-(5) Class 1 fatigue evaluations for the Resolved 3.9.3.1 -

safety / relief valve (SRV) discharge piping and downcomers '

(6) Method for combining dynamic responses Resolved 3.9.3.1 (7) Design of component supports Awaiting further --

information (8) Systems crawings for inservice testing Resolved --

(9) Fuel rod mechanical fracturing- Under review --

(10) Fuel assembly structural damage from Under review --

external source's -

(11) Fuel rod bowing Resolved 4.2.3.1 (12) Overheating of gadolinia fuel pellets Under review --

(13) Automatic restart capability for reactor Awaiting further --

-- core-isolation cooling (RCIC) system information (14) Modification to prevent spurious--- Awaiting further --

isolation of RCIC system information (15) Emergency procedures review Awaiting further --

information (16) ADS, low pressure cooling system (LPCS), Awaiting further --

and low pressure coolant injection information (LPCI) setpoint -

(17) RCIC system Awaiting further --

information (18) SRV position indications Awaiting further --

information (19) Additional accident monitoring Awaiting'further --

instrumentation information

- v

Xtem Status us Section (20) Rod block monitor Resolved 7.6.2.3 (21) Mitigating core damage training Awaiting further --

information (22) Assurance of engineered safety Under feview --

features (ESF) functioning and safety related system operability status (23) General plant guidance--building Resolved 9.5.1.5 design -

(24) Design-basis volcanic ash Resolved 2.5.1.3

1. 9 License Conditions Section 1.9 of the SER, SSER 1, and SSER 2 listed caveral probable license conditions. The updated list of these conditions is ;s follows:

Item Section (1) Ultimate heat sink --

(2) Channel box deflection . -

Deleted (4.2.3.1)

(3) Effects of high-burnup fission gas --

release on loss-of-coolant accident (LOCA) analysis (4) Inadequate core cooling (ICC) instrumenta- --

tio,n ana. lysis (5) Conditions for operations beyond cyclal --

(6) IE Bulletin 80-06, " Engineered Safety Features --

Reset Control" (7) Post-accident sampling. --

(8) Relocations of engine-mounted controls --

(9) Conformance of diesel generator fuel oil Deleted -

system (10) BWR startup or operating experience --

(11) Physical security --

(12) Prohibition of operations with partial --

~

feedwater heating (13) Remote shutdown system --

t'NP-2 SSER 3 1-5

_