ML19290D172

From kanterella
Jump to navigation Jump to search
Forwards NUREG-0565,Table 2-1,summarizing Bulletins & Orders Task Force Recommendations Requiring Followup by B&W Plant Owners.Requests That Util Be Reminded of Requirements
ML19290D172
Person / Time
Site: Crane Constellation icon.png
Issue date: 01/30/1980
From: Mazetis G
Office of Nuclear Reactor Regulation
To: Silver H
Office of Nuclear Reactor Regulation
Shared Package
ML111090060 List: ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8002200200
Download: ML19290D172 (3)


Text

.. _ _. -..

.,h!WI f,YfII P C 0.P;tf oke[Ei1eD JW 3 0 sd k3BRG R

Mazetis Chron G. Mazetis Docket No. 50-289 MEMORNiDUM FOR:

H. Silver, Licensing Project Manager, TMI-l FRCH:

G. Mazetis, Section Leader, Reactor Systects Branch, DSS SUSJECT:

TMI-1 IMPLEMENTATIO!,' 0F fu! REG-0565, " GENERIC EVALUATION OF SMALL BREAX LOCA BEHAVIOR IN B&W DESIGHED 177-FA OPERATING PLkITS" Recent distribution of flUREG-0565 us made culminating generic staff review of Ba'.i small breaks. Table 2-1 of this report (enclosed) stxx.arizes the B50TF reconaendations requiring followup by C&W plant owners. Met. Ed s' Juld be reminded of these requirements and that we are awaiting their cornitments and documentation of each area for THI-1.

Gerald R. Mazetis, Section Leader Reactor Systens Branch Division of Systems Safety

Enclosure:

As Stated cc:

Z. Rosztoczy P. Norian S. Newberry R. Vollter J. Voglewede T. Novak

Contact:

G. Mazetis, NRR Ext. 29406 8 0 0 20 0 0 2.c)O je CFFICE >

[

$URNAME >

g

_1119.aQ oa75 -

NRC Form 318A (4 79) NRCM 02040

  • w

=v...

..c.,

.m-a.

~.,..

s

.~m

TABLE 2-1 SCHEDULE FOR IMPLEMENTItG THE BULLETINS At40 GRDERS TASK FORCE RECOMMENDATIONS Reccccendation Schedule Number Recuired Action Date Excected Frecuencv of Small Break LOCAs 2.1.2.a Install automatic block valve closure system 07/01/80 cperational test of automatic bicek valve closure NOTE 1 system 2.1.2.b Evaluation of PORV opening probability during overpressure transients 05/01/80 2.1.2.c Reportirig of f ailures ano challenges to the PORV NOTE 2 2.1.2.d Evaluation of safety valve reliability 06/01/80 2.1.2.e Reporting of failures and challenges to safety valves NOTE 2 Small Break LCCA Analytical Model 2.2.2.a Analysis methods for SBLOCA (including evaluation of noding) 07/01/80 2.2.2.b Plant-specific calculations to show compliance with 10 CFR 50.45 01/01/81 2.2.2.c Evaluation of effects of core flood tank injection on SBLOCAs 07/01/80 Small Break LOCA Behavior 2.3.2.a Automatic trip for RCPs during SBLOCA - installed and operational 01/01/81 2.3.2.b Review and upgrade reliability and redundancy of nonsafety grade equipment upon which SBLOCA TMI-2 mitigation relies ACTION PLAN 2.3.2.c Minimum simulator training requirements for SBLOCAs 01/01/81 Staff Audit Calculations 2.4.2.a Additional staff audit calculations of B&W's SBLOCA analyses NRC ACTION 2-2

TABLE 2-1 (Continued)

Schedule Pecommentation Number Reouired Action Date Two-Phase Natural Circulation and Accommodation of Loss of All Feedwater 2.5.2.a Consideration of diverse decay heat removal path for THI-2 Davis-Besse Unit 1 ACTION PLAN Tennessee Valley Authority (TVA) Small Break Concerns 2.6.2.a Experimental verification of two phase natural circulation 01/01/81 2.6.2.b Instrumentation to verify natural circulation - installed and operational 04/01/81 2.6.2.c Analysis of plant response to a small break which is isolated, causing RCS repressurization and subsequent stuck-open PORV 06/01/80 2.6.2.d Analysis of plant response to a small break in the pressurizer spray line with a stuck-open spray line isolation valve 05/01/80 2.6.2.e Evaluation of effects of water slugs in piping caused by HPI and CFT flows 05/01/80

  • 2.6.2.f Evaluation of RCP seal damage and leakage during a SBLOCA 03/01/80 2.6.2.g Submit predictions for LOFT Test L3-6 (RCPs running)

(schedule for performing test not finalized)

PRE-TEST 2.6.2.h Submit requested information on the effects of noncondensible gases:

(1) justification for omission of radiolytic decomposition as a source of noncondensible gases, and (2) verification of predicted condensation heat transfer degradation 05/01/80

  • 2.6.2.1 Evaluation of mechanical effects of slug-flow on steam generator tubes 03/01/80 W.T.

1 - Confirmatory test of automatic block valve closure system shall be performed during the first refueling outage after installation of the system.

2 - PORV and safety valve failures and challenges:

failures shall be reported to the NRC promptly by licensees; challenges shall be reported in licensees' annual reports.

3 - TMI-2 Action Plan refers to NUREG-0660 entitled, " Action Plans for Implementing Recommendations of the Pr~ident's Commission and Other Studies of the TMI-2 Accident,"

Draft dated 12/10/79.

  • - Information requested in recommendations 2.6.2.f and 2.6.2.1 were previously requested from the B&W licensees in our letter from R. N. Reid, dated 11/21/79.

2-3