ML20052C748
| ML20052C748 | |
| Person / Time | |
|---|---|
| Issue date: | 07/02/1981 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML19250J298 | List: |
| References | |
| FOIA-82-93 NUDOCS 8205050460 | |
| Download: ML20052C748 (63) | |
Text
-
GENERIC ISSUES TRACKING SYSTEM (updated qu:rterly) b)
e" (status of Generic Issues as of 07/02/81)
The Generic Issues Tracking System (GITS) provides the status of the staff generic issues which are not OD reported as Unresolved Safety Issues (USIs) or TMI Action Plan Items.
Status of USIs is reported quarterly in the AQUA Book, HUREG-0606 and TMI action plan items are reported quarterly in the Action Plan Tracking System (APTS).
IP STATUS INDICATORS IN THIS REPORT ARE DEFIHED AS FOLLOWS:
1 TYPE SE l
USI Issues has been designated as a USI and status is reported in the AQUA Book (HUREG-0606) l S
Safety Issue l
E Environmental Issuo 8"
L Licensina improvement issue; activities aimed,at developing analysis or review procedures or improving understanding of phenomena j
2.
STATUS ACTIVE Item is currently under review.
IHACTIVE Ho work is currently underway in this item.
RESOLVED Issue has been completed and implemented.
ID l 3. E1AQ RED Trouble with item; serious slip ( > 1 year); severe resource shortage; tracking problems.
Ob YELLOW Any slip less than 1 year; potential red item.
GREEN Execution and/or implementation are going smoothly.
- 4. ERIORITY 8'
(value)
Assigned point score.
9 5.
IA3K A.P.
t YES Task action plan has been written.
IP f
HD Task action plan doesn't exist.
{
6.
TECHNICE RESOLUTION ID f COMPLETE Issue is technically resolved but not necessarily implemented.
INCOMPLETE Issue is not technically resolved.
l 7.
IMPLEMENIAIIDH 8b HOT STARTED g
IN PROGRESS 03 A COMPLETED Q-l 8.
UPDATED h
85 f
(mm/dd/yy)
Date of information reported in current report.
03 O
D*
43 1 M t1 P
Information in this report can be organized (sorted) by each of the OM 03 status indicators above.
That i s, a report can be provided (on request)
@@j l
of all active issues, all technically resolved issues, or any other listed n a category. Multiple parameters can also be sorted such as a list of all CHr o f"
active / safety / incomplete issues.
Q{g f*
l
___n
(J Mf_8 TYPE FLAG STAIyi_
PRIORITY TASK A.P.
IfCH. RE12 IMPLfMfHTATION TACS 8 UPDATED _
A-t
,USI ACTIVE YES INCOMPLETE IN PROGRESS 05/07/81 rs HRR AL SERKIZ (492-8437)
GIB/ DST U>
TITLE: Water Hanver DESCRIPTION: See AQUA Book HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 I)
PROBLEMS: See AQUA Book, HURE"-0606 I
.UE_8 M
FLAG STATUi_
PRIORITY TASK A.P.
TECH. RES.
IMPM MfMTAIIgH TACS 8 MPpAllL O
N _
A-2 USI ACTIVE YES COMPLETE IN PRUGRESS 05/07/81 HRR R.
SHAIDER (492-7876) ORB-5/DL TITLE:
Asymetric Blowdown Ioads on reactor Primary Coolant Systems DESCRIPTION: See AQUA Book, HUREG-0606
()
SCHEDULE: See AQUA Book, HUREG-0606 i
CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS: See AQUA Book, HUREG-0606 C) t U E _8 TYPE FLAG STATUS _
PRIORITY TASK A.P.
TEC_y, RES2 IMPLEtLENT ATION TACS 4 UP_yATED A-3 USI ACTIVE YES INCOMPLETE NOT STARTED 05/06/81 RES J. STROSHIDER (427-4262) MMRB/RSR lI TITLE: Westinghouse Steam Generator Tube Integrity DESCRIPTION: See AQUA Book. HUREG-0606 SCHECULE: Sco AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606
()
PROBLEMS: See AQUA Book, HUREG-0606 O
O n
F 0
0 0
0 0
O EUE.8 TYPE FLAG
_ STATUE _
PRIORITY TAf. A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATEQ_
A-4
.USI ACTIVE YES IHCOMPLETE HDT STARTED 05/ 0 F/81 RES J.
STROSHIDER (427-4262) Mr1RB/RSR E
TITLE:
CE Steam Generator Tube Integrity DESCRIPTIDH: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS: See AQUA Book, HUREG-0606 iUE 8 TYPF FLAG STATUS PRIORITY TASK A.P.
IECH, REL.
ItLP1f_M_f N T A T I O3 TACS 8 U P_Q A_If D__
A-5 USI ACTIVE YES INCOMPLETE HOT STARTED 05/07/81 RES J. STROSHIDER (427-4262) Mi1RB/RSR TITLE:
B8W Steam Gnnerator Tube Integrity DESCRIPTIDH: See AQUA Book, HUREG-0606 Sk SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS: See AQUA Book, HUREG-0606 S
VE 8 TYPE FLAG STATUS PRIORITY TASK A.P.
IfCH. R ES IMPLEMENTATION TACS 8 UPDATED m
A-6 USI RESOLVED YES COMPLETE C0t1PLETED S'
TITLE: MARK I Short Term Program DESCRIPTION: See HUREG-0408 SCHEDULE:
CURRENT STATUS:
IP PROBLEMS: HUREG-0408, Dec. 1977 i
.UE 8 TYPE FLAG STATU1_
PRIORIII TASK A.P.
TECH. RES.
IMEifMENTATIQB TACS 8 UPDATED Ub A-7 USI ACTIVE YES COMPLETE IN PROGRESS 05/07/81 HRR B. SIEGEL (492-9409) ORB 2/DL TITLE:
MARK I Long Term Program i
DESCRIPTION: See AQUA Book HUREG-0606 IE SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS: HUREG-0661, July, 1980 g,
I db O
O' P'
i GP f
()
E_5 TYPE FLAG STATUi_
PRIORITY TASK A.P.
TECH, REi.
JUPLfdfNTATIQH TACS 8 MPDATED_
"i USI ACTIVE YES IHCOMPLETE NOT STARTED 05/07/81 O'
GIB/ DST Sj 8
CLIFF ANDERSON (492-9424)
HRR MARK II Containment Pool Dynamic Leads - Long Term Program TITLE:
DESCRIPTIDH: See AQUA Book, HUREG-0606
~
0
?;j SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, t;UREG-0606 O
F:
PROBLEMS: HUREG-0487 f_8_
lYP_E
__ FLAG _
_ST ATUL PRICRITY TASK A.P.
TECH. RE JUP(fM_gNI ATION TACS 8 UP_D A TfL m9 USI ACTIVE YES C0llPLETE NOT STARTED 05/07/81
[:
HRR W. MIHHERS (492-7581)
DST
(.
TITLE:
ATWS s
DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606
}
4 CURRENT STATUS: See AQUA Book, NUREG-0606 0
PROBLEMS: HUREG-0460 Vol.
1, 2,3,4 TYPE
_ FLAG STATUS _
PRIORITY TASK A.P.
_T E C H. RES.
IUPLEMENTATIDH TACS 8 QEDAlfD_
YES COMPL ET E IN PROGRESS 05/07/81 10 USI ACTIVE l
HRR R. SHAIDER (492-7876) ORB-5/DL TITLE:
BWR Feedwatnr Ho=zle Cracking DESCRIPTIDH: See AQUA Book, NUREG-0606 O
SCHEDULE: See AQUA Book, HUREG-0606 l
CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS: HUREG-03f2 0
l l
t 1
l 6
l l
1 0'
0' l
l 0
1 l
l E---_
EF L
L JL4 TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED
<-11 USI ACTIVE YES INCOMPLET E NOT STARTED 05/07/81 l
C)
HRR R. JOHHSON (492-7385)
GIB/ DST TITLE:
Reactor Vessel Materials Toughness DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 d>
PROBLEMS:
ULJ!
TYPE FLAG _
STAJMS_
PRIORITY TASK A.P.
TECH. REi.
IMPLEMENTATIOM TACS #
UPDATED _
8>
L-12 USI ACTIVE YES INCOMPLETE NOT STARTED 05/07/81 HRR R. JOHHSON (492-7385) GIB/ DST TITLE:
Fracture Toughness of Steam Generator and Reactor Coolant Pump d>
Supports.
DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Bock, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 d>
PROBLEMS:
jf J TYPE FLAG
_,.1T_A Ijli_.
PRIORITY TASK A.P.
TECH. RES.
.LMP LEMf H_T A T I ON TACS #
UPDATED P. - 13 S
ACTIVE YES CONPLETE IN PROGRESS 01/15/81 8>
HRR E. HEMMINGER (492-9480) MEB/DE TITLE:
Snubber Operability Assurance DESCRIPTION: A substantial number of licensee event reports have been submitted on snubber malfunctions.
This has lead to an HRC d>
concern regarding the effect of snubber malfunctions on plant safety.
For a complete problem description of task, see HUREG-0371. Hovember 1978.
SCHEDULE: No schedule for completion of task implementation has d>
been established.
CURRENT STATUS: For operating plants, standard Technical Specification 3/4.7.9 (3/4.7.5 for BWRs) has been issued.
For CP and OL reviews, SRP 3.9.3 has been updated to include snubbers, and will be issued by MAY d>
198 1.
In addition, a snubber Regulatory Guide was issued for comment in February 1981 The combination of these documents will provide guidance and control on snubbers from the manufacturer to the user.
PROBLEMS:
d>
O
['
d>
O O
l t
O
n (J
E_#
.T-YP E FLAG _
ST ATUL PRIORITY TASK A.P.
lEC_B. RES.
IMP 1EMENTATION TACS #
UPDATED _
A-14 S
INACTIVE YES INCOMPLETE HOT STARTED 05/07/81 i
O
,e NRR M. HUM (492-7398)
TITLE:
Flaw Detection i
DESCRIPTIDH: This problem involves assessing inservice inspection and flaw detection techniques and providing regulatory guides for use by the staff.
Input will also be provided to the ASME Code,Section XI II on flaw detection techniques.
Tor a detailed description of task, see HUREG-0371 SCHEDULE: No schedule established.
II CURRENT STATUS: Work has been suspended - no activity on this task.
PROBLEMS:
P UE #
TYPE FLAG
_ STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
MPDATED_
II A-15 5
YES 05/07/81 HRR PHIL MATHEWS (492-8301)
CEB/DE TITLE:
Primary Coolant System Decontamination and Steam Generator Chemical Cleaning DESCRIPTIDH: See HUREG-0371 for Task Description.
II SCHEDULE: No schedule established.
CURRENT STATUS: Not determined.
PROBLEMS:
9
.T_A_EK A. P.
IECH, RE11 IMPLEMEHI A_IIO_li TACS #
UPDATED _
A UE #
TYPE FLAG STATUS _
PRIORITY Q-16 S
ACTIVE YES INCOMPLETE IN PROGRESS 05/11/81 HRR SUMMER SUN (492-9499) CPB/DSI GP TITLE:
Steam Effects on BWR Core Spray Distribution DESCRIPTION: During tests conducted in Europe and later confirmed by G.E.,
it was discovered that the presence of steam and pressure in and above the upper core region could adversely affect the distribution of (P
flow from certain types of core spray nozzles.
See HUREG-0371 for a complete task description.
k SCHEDULE: Task is scheduled to be completed during FY-1982.
CURRENT STATUS: The final series of nozzle tests are currently GP being conducted by GE at their facility in Lynn, Mass.
Information from this test series should provide sufficient information for the HRC to reach final conclusions on Task A-16 and to completely develop and document staff GP conclusions.
PROBLEMS:
l l
VE #
TYPE FLAG STATUS _
PRIORITY TASK A.P.
IECBm_RE11 IUPLEMENTATLOM TACS #
UPDATED GP A-17 USI ACTIVE YES INC0t1PLETE IN PROGRESS 05/19/81 I
FRANK C0FFMAN (492-8058)
RRAB/ DST TITLE:
Systems Intnraction GP DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: A-17 will no longer be worked as a USI.
Responsibility for continuation of the effort is with the RRAB of DST GP.
PROBLEMS:
i 7
b)
SUE 8 TYPE
_ELAG
_SIAIUS_
PRIORITY TASK A.P.
TECH. RES1 IUPLEMENTATION TACS #
UPDAlgD_
A-18
. 5 IHACTIVE YES INC0f1PLETE HOT STARTED 01/26/81 HRR SHOU HOU (492-9474) MEB/DE d>
TITLE:
Pipe Rupture Design Criteria DESCRIPTION: This task involves development of consistent pipe rupture criteria, evaluation of the break exclusion region of piping in containment penetra tion areas and development of composite design GP recuirements of piping systems for abnormal events and normal operation see HUREG-0371 for a complete task description.
SCHEDULE: No schedule established.
CURRENT STATUS: Ho work in progress.
PROBLEMS:
Ik SUE #
TYPE FLAG STATU1_
PRIORITY TASK A.P.
TECH. RES.
IMPLEMEHIAILQH TACS #
VPDATEQ_
Sk A-19 S
ACTIVE YES INCOMPLETE HOT STARTED 01/27/81 HRR BILL MORRIS (492-9435)
ICSB/DSI TITLE:
Digital Computer Protection System DESCRIPTIDH: A need exists to standardize the safety review of reactor d>
protection systems incorporating digital computers, since digital technology is considorably different from the analog technology previously used for RPS systems.
The technology is rapidly changing and needs to be assessed.
SCHEDULE: Schedule not available.
Ik CURRENT STATUS: Current OL reviews are being conducted on an ad hoc basis.
A joint effort (HRR with ORHL as a consultant) and RES will be directed toward development of a Regulatory Guide for use in subsequent reviews.
PROBLEMS:
Gk
>UE #
TYPE FLAG STATUi_
PRIORITY TASK A.P.
IECH, RES.
IUPLEUENTATION TACS #
UPDATED L-20E E
ACTIVE YES INCOMPLETE NOT STARTED 01/23/81 Ob HRR G. E. GEARS (492-8280)
EEB/DE TITLE:
Impacts of the Coal Fuel Cycle DESCRIPTION: The purpose of this task is to provide a technical basis for the detailed generic assessment of the environmental effects of Sh using coal for generating electricity.
See HUREG-0371 for a complete task description.
SCHEDULE: Hot scheduled.
CURRENT STATUS: ESRPs and Regulatory Guide 4.2 will be revised when U>
reviews of contractor report HUREG CR/1060 is completed.
Work has been suspended pending availability of staff.
PROBLEMS:
P P
i SD
}
O
i
()
j i
)E :
IYPE FLAG
_STATUi_
PRIORITY TASK A.P.
IECH. RES.
IMPLEMENTATION TACS #
MPDAlfQ_
=
A-21 S
ACTIVE YES IHCOMPLETE IN PROGRESS 04/00/81 HRR JACK KUDRICK (492-0415)
CSB/DSI TITLE: Main Steamline Break Inside Constinment - Evaluation of Environmental Conditions for Equipment Qualification DESCRIPTIDH: To resolve the concerns regarding the evaluation of i
appropriate environmental conditions following a postulated MSLB
(
accident inside containment.
This task supports USI A-24.
See j
HUREG-0371 for a complete task description.
SCHEDULE: Will be completed in early FY-82.
II
\\
CURRENT STATUS: Interim criteria have been established for purposes of environmental qualifications, about three man months will be required to finalize criteria.
PROBLEMS:
9 s
TYPE FLAG
_ STATUS _
PRIORITY TASK A.P.
TECH. RES.
JMP_LFM HIATI_08 TACS e UPDATED __
J-22 5
INACTIVE YES 1HCOMPLETE HOT STARTED 04/00/81 S
HRR TITLE:
PWR Main Steamline Break, Core, Reactor Vessel and Containment Building Response DESCRIPTION: This task derived from issues 1 and 15 of HUREG 0318.
GD Issue 1 questioned operation of nonsafety grade equipment following a MSLB.
Issue 15 is concerned with the Mechanical response of the pressure vessel following a MSLB.
See HUREG-0371 for a complete task description.
(P SCHEDULE: No schedule established.
Ho work was ever initiated on this task.
Issue 15 CURRENT STATUS:
is included in a proposed new issue "repressurization following thermal shock".
9 PROBLEMS:
UE #
TYPE FLAG STATUS _
PRIORITY TASK A.P.
TECH. RES.
,lDPLEMEHTATION TACS #
HPDATED l
<Q-25 S
ACTIVE YES COMPLETE 1H PROGRESS 05/00/61 GP i
f NRR JIM SHAPAKER (492-9416)
CSB/DSI l
TITLE:
Containment Leak Testinq This task was developed to incorporate needed changes 9
DESCRIPTIDH:
to Appendix J to reflect current understanding and licensing practice.
A complete task description can be found in HUREG-0371.
SCHEDULE: No schedule available this report.
i CURRENT STATUS: A revision to Appendix J is being prepared and will GP i result in a rulemaking proceeding.
PROBLEMS: Hone.
4 9
0 W
p
.T7
(/
l UE :
IYPE FLAG
_11ATyi_
PRIORITY TASK A.P.
TECH. RES.
IMP 1fMENTATION TACS 8 MPRAlfD_
A-24 USI ACTIVE YES INCOMPLETE IN PROGRESS 05/00/81 HRR A.
Szukicwicz (492-9427)
GIB/DSI
()
TITLE:
Qualification of class I-E Safety Related Equipment DESCRIPTION: See AQUA Book, HUREG-0606.
SCHEDULE: Sen AQUA Book, HUREG-0606.
CURRENT STATUS: See AQUA Book, HUREG-0606.
GP PROBLEMS: See AQUA Book, HUREG-0606.
j QE_s TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED GD A-25 5
YES HRR Faust Rosa (492-7635) PSB/DSI TITLE:
Hon Safety loads on Class IE Power Sources DESCRIPTION: The safety issue addressed by this task is whether or not GP the reliability of class IE power sources is significantly affected by allowing the sharing of these sources by loads that perform safety functions and loads that perform normal plant functions.
See HUREG-0371 for a completo task description.
GP SCHEDULE: Not available.
CURRENT STATUS: Not available.
PROBLEMS:
D UE #
TYPE
._ELAQ_
STATUS _
PRIORITY TASK A.P.
IECH. RES.
IMPL EM_IMIAII_03 TACS #
MPDATED_
A-26 USI RESOLVED YES COMPLETE IN PROGRESS 05/00/81 HRR DAN GARHER (492-8430)
ORAB4/DL D
TITLE:
Reactor Vessel Pressure Transient Protection DESCRIPTIDH: See AQUA Book, HUREG-0606, Status of USIs for which Technical Resolution is complete.
SCHEDULE: Sen AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606.
PROBLEMS:
D D
q l
D e
i
-- J
~
db
(
E_8 JZEg FLAG STATUS _
PRIORITY TASK A.P.
IECH. RES.
IMPLEMENTATION TACS #
UPDATgQ.
p
-27
'L RESOLVED YES COMPLETE COMPLETE 05/00/81 C) i HRR Gerald Ma:etis RSB/DSI TITLE:
Reload Applications DESCRIPTION: Provide a comprehensive quidance document for use of h
Technical reviewers for the review of core reload applications.
Ib SCHEDULE:
CURRENT STATUS: Complete PROBLEMS:
f>
f E_8 TYPE FLAG _
STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED-
-28 5
YES HRR 8"
TITLE:
Increase in Spent Fuel Pool Capacity DESCRIPTION: Develop a generic environmental impact statement and prepare for rulemaking proceeding on definition standards and criteria for spent fuel pool expansion.
SCHEDULE: Unknown CURRENT STATUS: Unknown PROBLEMS:
'f_ 8 TYPE FLAG
_1TATM1_
PRIORITY TASK A.P.
LECH. RES.
IMPLEMENTATIDH TACS #
UPDATED _
-29 S
ACTIVE YES INCOMPLETE Ot/00/81 i
RES T0f1 ALLEH (427-4181)
UE TITLE:
Hucicar Power Plant Design for the reduction of Vulnerability to Industrial Sabotage.
DESCRIPTION: See HUREG-0371 for task description.
SCHEDULE: Not available.
8" CURRENT STATUS: An effort to determine requirements to compartmentalize plant areas to prevent sabotage is underway.
LASL is condveting vital area analysis.
Results of LASL work will serve as a starting point j
i identifyino generic requirements to compartmentalize.
In-houso study I"
of safety impacts will start in mid-1981.
PROBLEMS:
db JE 8 IIEE
_EL A G _
STATUS _
PRIORITY TASK A.P.
IECH. RES.
IMPLEMENTATION TACS #
UPDATED 4-30 S
RESOLVED C0!1P L ET E HRR M. SRINIVASH (492-7233)
PSB/DSI TITLE:
Adequacy of safety - safety related DC power supplies.
IP DESCRIPTIDH: See HUREG-0371 for task description.
SCHEDULE: Implementation schedule not established.
CURRENT STATUS: HUREG-0666, "A Probabalistic Safety Analysis of DC Power Supply Requirements for Nuclear Power Plants" was issued in April
'81.
IP This report presents the technical resolution of A-30.
PROBLEMS:
O O
O i
n7
%)
EVE #
TYPE FLAG STATUS _
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED A-31 USI INACTIVE YES COMPLETE NOT STARTED 05/00/81 NRR Tem Novsak (492-7817)
,.3 ts TITLE:
RHR Shutd:wn Requirem:nts DESCRIPTION: See AQUA Book, HUREG-0616 SCHEDULE: Implementation not scheduled CURRENT STATUS: Impicmented on cps and Ols via SRP 5,4,7.
($
5-1 and RG 1,139 not stated on operating reactors.
PROBLEMS:
O LUE a ILP_E FLAG STAE S_
PRIORITY TASK A.P.
IE_C_H_, _R_EL.
E P(ft1ENTATIDH TACS #
UPDATE _D P
A-32 S
ACTIVE YES INCOMPLETE NOT STARTED 01/00/81 HRR
- 0. Rothberg (492-9566)
TITLE: Missile Effects (d
DESCRIPTION: This task involves development of specific licensing positions and bases for protection of nuclear plants against missile impact effects.
See HUREG-0371 for a complete task description.
gh SCHEDULE: There is no currently established schedule for this task.
CURRENT STATUS: EPRI is completing a series of full scale and reduced scale turbine missile impact tests and has completed a scries of tornado missile impact tests.
gp PROBLEMS:
'UE_e TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
D P_D AjLlyl, gh A-33 E
TITLE:
HEPA Review of Accident Risks DESCRIPTION: See HUREG-0371 g>
t r.H E DU L E : Unknown
.;RRENT STATUS: Unknown PROBLENS:
e
>UE F TYPE FLAG
__iBlV L PRIORITY TASK A.P.
LECH. RW R W ENTATIDH TACS #
UPDATER _
A-34 S
RESOLVED YES COMPLETE COMPLETE 01/00/81 HRR Bill Morris (492-9435)
ICSD/DSI g>
TITLE:
Instruments for Monitoring Radiation and Process Variables Durina Accidents DESCRIPTION: Develop criteria and guidelines for functional and operational capabilities required of the different classes of g>
instruments.
See HUREG-0371 for a complete task description.
SCHEDULE: Not applicable CURRENT STATUS: Complete PROBLEMS:
g>
e D
1h i
<=
I WP i
L -(3 5JJ _2 YPE FLAG STATUS PRIORITY VASK A.P.
TECH. RE&.
IMPLEMEHVATIDH TACS 4 QPRATED_
ACTIVE YES In Progress 01/00/81 HRR R.
Fitzpatrick i
TITLE:
Adequacy of Offsite Power Systems DESCRIPTION: To assess the reliability of offsite power systems.
3 See HUREG-0410 and issue 10 of HUREG-0138 for a detailed task f>
description.
SCHEDULE: SRP 8.3.1 revision scheduled to be complete by mid 81.
Also backfit of requirements to all operating reactors to be complete by mid 81.
f>
CURRENT STATUS: Resolution is formalized in SRP 8.3.1 All OLs since 1977 have complied with these requirements.
PROBLEMS: Hone P
DE :
TYPE FLAG STAIM1_
PRIORITY IASK_A.P.
_T ECH. REit IMPLEMENTATION TACS #
UPDATED _
A-36 USI ACTIVE YES CarlPLETE IN PROGRESS 05/00/81 HRR Bud Requa (492-8478)
ORB-3/DL
- b TITLE:
Control of Ileavy Loads Hear Spent Fuel DESCRIPTIDH: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book. HUREG-0606
$4 PROBLEMS:
Le TYPE FLAG STATME_
PRIORITY TASK A.P.
IECH _Egi.
IMPLEMENTATION TACS #
UPDAlgq_
d%
2 D-37 S
ACTIVE YES INCOMPLETE 01/00/81 HRR
- 0. ROTHBERG (492-9566)
SEB/DE TITLE:
Turbine Misslies DESCRIPTIOH: See HUREG-0137 for Task description.
fD SCHEDULE: Unknown CURRENT STATUS: EPRI is curretnly doing full and reduced scale missile tests. Most of the work to date on this task has been on turbine blade cracking.
1 PROBLEMS:
O F E_#
TYPE
_ FLAG _ _ STATUS _
PRIORITY TASK A.P.
TECH. RElm IMPLEMENTATIDH TACS #
UPDAlgD_
9 2
01/00/81 0-38 5
INACTIVE YES dhil NRR
- 0. ROTHBERG (492-9566)
SEB/DE TITLE:
DESCRIPTION: See HUREG-0137 for Task description.
SCHEDULE: Undetermined db ;
CURRENT STATUS: Hot determined 8
PROBLEMS:
O O
O db
LUE 8 TWE f#L OG STOTUS_,~
Pf9I OQIWY~
T09K D.
TECH.'REit ' IMPJ.ftENT AT_I_Q3 TACS 8 MPDATED.
}
A-39 USI ACTIVE YES INCOMPLEIE NOT STARIED 05/00/81 HRR Halsen Su (492-9422) GIB/ DST C)
TITLE:
Datermination of Safety Relief Valua Pool Dyntmic Loads
~
and Tempsrature Limits DESCRIPTION: See AQUA Book, NUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 C)
CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:
, U E_8 TYEE FLAG STATU1_
PRIORITY TASK A.P.
TECH. R Eli IMPLEMENTATION TACS 8 UPDATED A-40 USI ACTIVE YES IHCOMPLETE HOT STARTED 05/00/81 HRR Goutam Bagehi (443-5970)
EQB/DE TITLE:
Seismic Design Criteria - Short Term Program
- i DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606
- D PROBLEMS:
>UE 8 lYEE FLAG
_ STATUS _
PRIORITY TASK A.P.
Jigh __R Eiz I!1PLEMfHTATIO3 TACS 8 MPDATER_
A-41 S
INACTIVE NO IHC0t1PLETE NOT _STARIED 05/00/81
,1 HRR N. Anderson (492-8434)
GIB/ DST TITLE:
Long Term Seismic Program DESCRIPTION: This Generic Task involved long term research
'l program on scismic design.
It was never started as a generic issue and is being conducted by RES as the Seismic Safety Margins Research Program (SSMRP).
SCHEDULE:
CURRENT STATUS: Ho longer considered to be a generic activity.
PROBLEMS:
iUE 8 TYPE FLAG STATUi_
ERIORITY TASK A.P.
TECH. RES.
IMP 11 MENTATION TACS 8 MPQAlfQ_
A-42 USI ACTIVE YES COMPLET E IN PROGRESS 05/00/81 HRR Dick Clark (492-9797) ORB-2/DL TITLE:
Pipe Cracks in Boiling Water Reactors DESCRIPTIDH: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:
i me r I
~n l
(?
I b
FLAA_
,_SI A11[S_
P_RIORITl TASK A.P.
IECH. RES.
IMPLEM_ENTATION TACS 8 HPDATEQ_
-43.
USI ACTIVE YES INCOMPLETE NOT STARIED 05/00/81 F
HRR Al Serktz (492-8437) GIB/ DST it TITLE:
Containment Energency Sump Performance.
W DESCRIF.T IO N : See AQUA Book. HUREG-0606 SCHEDULE: See AQUA Book. HUREG-0606 gJ CURRENT STATUS: Sco AQUA Book, NUREG-0606 b
PROBLEMS:
I F
f 5_e TYPE
_ FLAG STATUS _
ER1_0RITY TASK A.P.
TECH. REli IMPLEMENTATION TACS 8 UPDATEQ_
r 1-44 USI ACTIVE YES INCOMPLETE NOT SIARTED 05/00/81 P
NRR Pat Baranowski (443-5921) RRBR/RES TITLE:
Station Blackout S'
DESCRIPTION: See AQUA Book, NUREG-0606 i
SCHEDULE: See AQUA Book, HUREG-0606
(
CURRENT STATUS: See AQUA Book, NUREG-G606 l
0 PROBLEMS:
h UE_8 TYPE FLAG _ _51AlyS_
PRIORITY TASK A.P.
TECH. R ES IMP (JMfHTATION TACS 4 MPDAlfQ_
L-45 USI ACTIVE YES INCOMPLETE 110T SIARTED 05/00/81 4
2 S
i HRR Andrew Marchese (492-8230) GIB/ DST 1
TITLE:
Shutdown Decay Heat Removal Requirements DESCRIPTION: See AQUA Book, NUREG-0606 l
SCHEDULE: See AQUA Book. HUREG-0606 i
l CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:
9 9
9 9
1 4
gr i
9 f-
kYP_g
,UE 8 FLAG STAIMS_
PRIORITY TASK A.P.
IRCl!m8E1.
Jt!!'L EMENT A TION TACS_t U!'D A T_f p, A-46 USI ACTIVE YES INCOMPLETE NOT SIARIED 05/00/81 HR2 Jshn Burna (492-9440)
GIS/ DST
(;
TITLE:
Soismic Qunlifienticn of Equipm:nt in Op; rating Plento DESCRIPTIDH: See AQUA Book, NUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HU P. EG- 0 6 0 6
$d PROBLEMS:
UE e TYPE FLAG
_}IAIUi_
PRIORITY TASK A.P.
TfCH. RES.
IMPLEMENTATION TACS MPDAlfD_
gh A-97 USI ACTIVE NO INCOMPLETE 05/00/81 HRR Andrew Szukiewicz (492-9427)
GIB/ DST TITLE:
Safety Implications of Control Systems
_s DESCRIPTIDH: See AQUA Book, HUREG-0606 e
SCHEDULE: See AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:
gh
'UE #
TYPE FLAG STATUE _
PRIORITY TASK A.P.
TECH. RE1.
IUPLEMEMTATION TACS #
UEDATED A-48 USI AC1IVE HO INCOMPLETE NOT STARTED 05/03/81 HRR Hewton Anderson (492-8434)
GIB/ DST em TITLE:
Hydrogen Control Measures and Effects of Hydrocen Burns on Safety Equipment DESCRIPTICH: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 gm CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:
O e
F
~
L Lj!
TYPE
_ELAG STATUi_
PRIORITY IASK A.P.
IfCH. RES.
IMPLEMENTATION TACS #
UPDATfQ_
k
-1 E
ACTIVE NO IHC0tlPL ET E IN PROGRESS 01/00/81 F
HRR T. Cain (492-4827)
EEB/DE F
v TITLE:
Environmental Technical Specifications
[
DESCRIPTION: Based on several years experience with facility licensing and a better understanding of EPA and HRC regulations, 3
it was decided to develop standarized Environmental Technical F
t Specifications (SETS).
This task is for the development of e
the SETS.
Final product will be either a HUREG report or as 5
Req. Guide 4.8.
k SCHEDULE: No schedule available.
F CURRENT STATUS: SETS have been developed for North Anna 1,
k.
Farley, Salem 1 and 2 and Sequoyah.
Draft SETS have been f
prepared for Pt. Beach, Trojan, Crystal River, Main Yankee, Indian Point and Palisades.
Rest of OLs will be corrected WP 1
as resources permit.
(
PROBLEMS:
L4 9
Lj!
IXEg FLAG STATUS _
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATEQ_
d
-2 E
ACTIVE 01/00/8i
]"
HRR Sidney Feld (492-4903) UFB/DE TITLE:
Forecasting Electricity Demand f>
DESCRIPTION: This task involves improving the HRC staffs V
capability to forecast electricity demand for the purpose y
of evaluating applicants need for power forecasts in k
individual licensing cases.
WP SCHEDULE: To be completed during FY-82.
W CURRENT STATUS: Model i s being changed to incorporate technological H
changes in electricity use which can be used to treat appliance and equipment saturation.
Also the methods of estima'.ing general WP a
service area demand from state level forecasts are being improved.
y PROBLEMS:
,il f
i_a 11EE FLAG STATU1_
PR.IORITY TASK A.P.
TECH. RE12 IMPLEMENTATION TACS #
UPDATED j
-3 L
IHACTIVE NO INCOMPLETE HOT STARTED NRR 1
TITLE:
Event Categorizaiton WP y
DESCRIPTION: This task is to categorize postulated transients 3
and accidents and define acceptance criteria for the various y
catcqories.
4 d'
SCHEDULE: None f'
CURRENT STATUS: Unknown PROBLEMS:
.i g
)
SP f
I4 W
l 6
f
)
r
U-4
-L UNKNOWN LLO N
() T\\
NRR Sammy Dizu RSB/DSI TITLE:
ECCS Ralir.bility DESCRIPTION: Thig tzsk involvoa dsvaleping end rpplying numsrical relisbility qmals to tha liccneing precs2s.
()
SCHEDULE: None CURRENT STATUS: Existing IHEL contract but status not known.
PROBLEMS:
O UE #
TYPE FLAG STATUS _
PRIORITY TASK A.P.
ILQH. R EL.
1HP_LEMRRAll0_E TACS #
LLPD A T_EL O-5 S
INACIIVE NO INCOMPLETE NOT STARTED 01/01/88 HRR
- 4 TITLE:
Ductility of two way slabs and shells and Buckling Behavior of Steel Containments.
DESCRIPTIDH: This task includes two separate tasks.
They will be redefined and prioritized separately.
SCHEDULE: Hot scheduled CURRENT STATUS: Same work is being done on containment buckling i
l by the Structural Engineering Branch of DE.
PROBLEMS:
% {
UE #
TYPE FLAG STAlU1_
PRIORITY TASK A.P.
IECH. RES.
IMPLEMENTATION TACS #
UPDATED _
B-6 S
ACTIVE YES IHCOMPLETE HDT STARTED 01/00/81 HRR Shou - Hien Hou (492-9474) MEB/DE TITLE:
Loads, Load Combinations, Stress Limits DESCRIPTION: This task will define how design loads should be combined
(
on components, piping systems and structures and the stress limits f
to be used in evaluating structural integrity and operability when subjected to these loads, t
d SCHEDULE: Revision of SRP 3.9.3 to be completed in March 81 d
and revision 2 of HUREG-0484 in December 1981 CURRENT STATUS: HUREG-0484 regarding load combination methodology only has been issued.
Criteria regarding acceptability of using SRSS for combining dynamic responses is planned to be implemented on all Mark II plants as part of OL reviews. Minor revi sion of SRP 3.9.3 is underway and Rev. 2 of HUREG-0484 is planned by
]
December 1981.
PROBLEMS:
I MW p
0F r
ILs TYPE FLAG _ _ STATUS _
PQIORITY TASK 4.P.
VECH. RES.
IMPLEMENTATION TACS #
MPDAIJQ_
-7 L
INACTIVE NO INCOMPLETE 03/00/88 f
NRR Walt Pasadag (492-7193) AEB TITLE:
Secondary Accident Consequence Modeling DESCRIPTION: Develop more rollable models and associated computer capability for assessing radiological consequences of accidents Ob
+
that could result in release of radioactivity through secondary systems.
SCHEDULE: Hot available - estimated one professional staff year to complete.
CURRENT STATUS: Heeds re-evaluation and formulation of task objective.
Some progress has been made.
PROBLEMS:
9 fjl Il TYPE FLAG _
STATUS _
PRIORITY IA3K A.P.
IECH. RES.
IMPLEMENTATION TACS s MPDATED_
l-8 5
IHACTIVE H0 1HCOMPLEIE NOT STARTED 03/00/81 HRR RSB/DSI F
TITLE:
Locking out of ECCS Power Operated Values DESCRIPTIDH: Re evaluation of the requirement for physical lockinq f
out of electrical sources to specific motor operated valves using j
a systems approach. Will consider such items as probability of UP 1
a spurious signal, time to reactivate, status of signal lights,
[
and other areas as necessary.
SCHEDULE: Hot established.
CURRENT STATUS: Unknown 8'
PROBLEMS:
LE_8 TYPE FLAG _,}TATUS PRIORITY TASK A.P.
IfCH. RES.
JMP(EMENTATION TACS #
UPDATED _
f" B-9 5
IHACTIVE NO INCOMPLETE HOT SIARTED HRR Al Unaaro (492-8024) PSB/DSI TITLE:
Electrical Cable Penetrations of Containment DESCRIPTION: Re-evaluate current licensing criteria for the design 8"
and qualification testing of electrical penetrations in the reactor containment.
SCHEDULE: Hot available.
CURRENT STATUS: Unkneen GF PROBLEMS:
9 l
l i
O P
9
f
' SUE I.L.E FLAG
_ STATUL PRIORITY TASK A.P.
IECH. RES.
It1PLEMENTATION TACS 8 8-10 S
ACTIVE YES INC0t1PLEIED HOT STARTED 04/00/81 EPAAE Q, P
HRR Mal Fields (492-9417) CSB/DSI O.
TITLE:
Behavice of BWR Mark III Containments DESCRIPTION: Staff evaluation of the Mark III containment and documentation of the method used to validate the analytical models and assumptions needed to predict containment pressures in the event of a LOCA.
SCHEDULE: Completion of task in early 1982.
CURRENT STATUS: Issued set of questions to G.E.
In November 1980.
Response is due July 1981 NP,C position should be developed by August 1981.
PROBLEf15 O
S U E_ 8 J1P_E FLAG STATUS PRIORITY TASK A.P.
TECH. RF1 IMPLEMENTATION TACS #
UPDATED 8-11 L
HQ NRR Jack Kudrick (492-9415) CSB/DSI TITLE:
Subcompartment Standard Problems DESCRIPTION:
SCHEDULE: Not scheduled CURRENT STATUS: Unknown PROBLEMS:
5UE #
TYPE FLAG STATUS PRIORITY TASK A A TECH. RES.
IMPLEMENTATION TACS #
UPDATED 8-12 L
HD 8
NRR TITLE:
Containment Cooling Requirements (Non LOCA)
DESCRIPTIDH: The rationale for normal and past accident cooling will be reviewed to determine the adequacy of the 8
design requirements imposed on containment ventilation systems.
SCHEDULE: Unknown CURRENT STATUS: Unknown PROBLEMS:
O, Os l
O-l 9>
9s
~
W JE a
'j_Yf_g FLAG STATUS PRIORITY TASK A.P.
J_F,QJI RES.
IMPLEMENTATION TACS #
UPDATED 5'15 L
HRR Jack Kudrick (492-9415)
CSB/DSI P
j TITLE: Marviken Test Data Evaluations l
DESCRIPTION: Correlate the Marviken containment test data and compare the results with existing computer programs.
SCHEDULE: None CURRENT STATUS: Unknown PROBLEMS:
9 JD TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED 3-14 USI TITLE:
P DESCRIPTION: This task is included as part of USI A-48 SCHEDULE: N/A CURRENT STATUS: N/A PROBLEMS:
J TYPE FLAG
_jTATUS_
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED D
B-15 L
ACTIVE NO F
HRR Larry Ruth (492-9423)
CSB/DSI i
TITLE: Contempt Computer Code Maintenance DESCRIPTION: This is a continuing effort and is not a generic safety issue.
P SCHEDULE: N/A CURRENT STATUS: Continuing PROBLEMS:
p P
1 P
i 0
9 1
1 4
0 F. 1
lUE #
TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED D-16 5
TITLE: Protection egiinst psstulatgd piping feilurs in fluid systems Outsids Centainment DESCRIPTIDH: This task has been incorporated into task A-18 l-
" Pipe Rupture Design Criteria" IS SCHEDULE: N/A CURRENT STATUS: N/A l
PROBLEMS:
(
IP JLE #
TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED O-17 5
l 4>
TITLE: Criteria for Safety Related Operator Actions l
DESCRIPTIOH: Task involves the development of a time criterion for l
safety related operator actions and includes determination of whether or not automatic ECCS realigment will be required.
db
['
SCHEDULE: None CURRENT STATUS: This task is superceded by TMI Action Plan items I.A and I.C.
l PROBLEMS:
GD l
Ug #
TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED l
Q-18 USI d>
TITLE: Vorterx Suppression Requirements for Containment Sumps.
DESCRIPTION: This task is included as part of USI A-43 " Containment Emergency Sump performance.
4D SCHEDULE: N/A CURRENT STATUS: N/A PROBLEMS:
O l
e O
O O
O O
6%
k 4'
jf_#
lYEg FLAG.
_ STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED Bo19
'L th I
4 TITLE: Thermal Hydraulic Stability DESCRIPTION: This task involves the development of the analytical methods necessary for the staff to perform independent calculations 96 to check vendor analyses of Thermal Hydraulic Stability.
SCHEDULE: None CURRENT STATUS: Unknown PROBLEMS:
9 TYPE FLAG STATUS PRIORITY TA3K A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED _
I
-20 L
N0 P
TITLE: Standard Problem Analysis DESCRIPTIDH:
SCHEDULE: None CURRENT STATUS: This is an ongoing task and is not a t'afined safety issue.
9 PROBLEMS:
UR #
lYEE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED
.B-21 L
TITLE: Core Physics GF l
DESCRIPTIDH: This task is not a generic safety concern.
SCHEDULE: None CURRENT STATUS: Ongoing PROBLEMS:
9 i
p I
1 P
9 0
9 f
d E_t TYPg FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED l
-22 L
er TITLE: LWR Fusi DESCRIPTION: This task i s not a gInaric safety concern.
SCHEDULE: Hone g
i CURRENT STATUS: Hone er PROBLEMS:
E_#
TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATIDH TACS 4 UPDATED em I.
-23 L
H0 TITLE: LMFBR Fuel I
DESCRIPTION: This task is not a generic safety concern.
er SC'MDU L E: None h
CURRENT STATUS: Unknown y
PROBLEMS:
e l_8 TYPE
_ FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED
(
-24 USI ACTIVE NO is GP TITLE: Seismic Qualification of Electrical and Mechanical Components
~
DESCRIPTIDH: This task is included in USI A-46 " Seismic Qualification f
of Equipment in Operating Plants.
)
SCHEDULE: None er P
CURRENT STATUS: Superceded by A-46 PROBLEMS:
h a
k s'
EP t,-
[i t
4>
0 4>
1 l
i t
1l d
(1 i i
f
/
/
(%
o s'
3 T
w
-25 L
ACTIVE _
PRIORITY TASK A.P.
TECH. RES2 1MPLEMENTATION TACS 8 UPDATED-
[
E_8 IYP]
FLAG STATUS.
C) y NO COMPLETE IH PROGRESS 01/00/81 HRR M. Hartman (492-9478) MEB/DE TITLE: Piping Benchmark Problems f
DESCRIPTIDH: This task consists of developing benchmark problems for structural analysis and design of piping systems for use in reviewing
/
f>
applications for construction permits, SCHEDULE: Technical resolution scheduled for end of FY-82.
"j CURRENT STATUS: Results of this task have been used to implement provisions in IE Bulletin 79-07 regarding dynamic analysis y
verification of structural computer programs. Requirements in Sk SRP 3.9.1, using the results of this task, will be specified in the upcoming revision of the SRP.
O PROBLEMS:
pm s
6 E_8 TYPE FLAG STATMS_
PRIORITY TASK A.P.
JECH. RES2 1MELEMENTATION TACS 8 UPDATER _
-26 S
ACilVE YES INCOMPLETE IN PROGRESS 01/00/81 1
W>
lj HRR J. Rajan (402-9475) MEB/DE TITLE: Structural Integrity of Containment Penetrations
)
DESCRIPTION: This task involves an evaluation to assess the adequacy 4
of specific containment penetration designs from the point of view
.)
of structural integrity and inservice inspection requirements.
GP g:
SCHEDULE: Unknown j
i CURRENT STATUS: The task involves 2 issues.
The first is structural evaluation of welded flued head assemblies.
This part has been i]
resolved.
The second area involves the volumetric examination 6>
as required by ASME Code,Section XI.
Thi s issue is only partially
[
resolved and additional independent verification needs to be L
performed.
No systematic implementation plan has been developed WP to date.
}
PROBLEMS:
1_8 IIPE FLAG _
STATUS _
PRIORITY IASE A.P.
IECH. Rgli IMP L EM EHI A TIDH TACS #
UPDATED _
dP I
=27 L
ACTIVE N0 IHCOMPLETE HOT SIARTED 01/00/81 NRR M. Hartman (492-9478) MEB/DE TITLE: Implementation and USe of Subsection NF d>
DESCRIPTION: This task is to develop a staff position with regard to use of subsection HF in licensing actions not applicable to plants which predate subsection HF.
SCHEDULE: FY-82 CURRENT STATUS: Eventual goad is to endorse in 10CFR 50.55a.
A f*
regulatory guide on jurisdiction and design nf mechanical supports i
i is being prepared.
1 PROBLEMS:
d>
,t o
k dk
(
i GP i
t gr i
e f
Kll loM3 401L J@dh lM LikDO M N
382S$MRODE XOMi-Q LMQlElk
[
FT28 E
ACTIVE NO INCOMPLETE NOT STARTED 02/00/81 HRR R.
Codall (492-8117) HGEB/DE C)
TITLE: Radionuclide/Sedimsnt Transpent Program DESCRIPTION: This task is to develop radionuclids/ssdimant transpant models that have been field verified.
SCHEDULE: To be completed in 1981.
43
-I CURRENT STATUS: The fate of radionuclides released to surface waters (i.e.),
lakes, estuaries, ocenas is complicated by the interaction of radionuclide with sediments.
Few analystical methods estimate the effects of sediments on the transport of radionuclides through the hydrophere.
There are many questions on sediments in the PDEIS l
(NUREG-0683).
Sediments effects were an important part of the l
Liquid Pathway Generic Study (HUREG-0440) and FES-III (Floating Huc1 car Power - HUREG-0502).
The staff is pursuing research leading to quantification of the effects of sediment.
Predictive models must be developed and verified with data o
obtained from actual radionuclide/ sediment environments.
I Research programs have been established resulting in models applicable for tidal, non-tidal, esturaries and oceans.
Data collection is complete for non-tidal rivers and underway for estuaries and tidal rivers.
PROBLEMS:
LE_8 TYPE FLAG STAIU1_
PRIORITY TASK A.P.
IECH. Rfit IMPLEMENTATION TACS #
UPRATED 5-29 L
ACilVE HO IHCOMPLETE 02/00/81 l
HRR R.
Codell (492-8117)
HGEB/DE TITLE: Effectiveness of Ultimate Heat Sinks DESCRIPiION: Evaluation of the anticipated performance of Ultimate Heat Sinks under design basis conditions requires the use of predictive analytical models.
Most such models are not fully verified due to the lack of actual high quality performance data.
i The models must be used in a highly conservative modo and the 1
analysis must firstly rest on preoperational data.
The methodology for finding the design basis condition for evaluating the Ultimate Hoat Sink have previously been only vaquely defined to correct the deficiencies.
The staff has resently prepared HUREG-0693 for Ultimate llent Sink Cooling Pond analysis and is presently preparing HUREG (draft) for 4>
Spring Ponds.
A future HUREG compares the results of PHL cooling pond and Spring final performance to NRC model predictions.
These HUREG documents develop indetail the staff's position on what should be required for Ultimate 5?
Heat Sink cooling pond and spring pond performance appraisals.
Performance criteria for UHS may be too conservative.
Currently, there is no way to refine the early predictive estimate until G) the plant is essentially ready to operate.
SCHEDULE: To be completed in 1982.
CURRENT STATUS: The staff has prepared a User Heed Letter for RES asking for validation of existing cooling pond hydraulic models Q?
against known field data so that these more advanced models can be used for UHS appraisals.
PROBLEMS:
T O
-_._.__..j M. Z. s.V5 c
8 M
FLAG STATUL PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS 8 U P_D A_lE D _
ACTIVE HO 02/00/82 he 30 L"
HRR M.
Fliegni (492-8003)
HGEB/DE C) 7 TITLE: Drsign Basis Flcods 8 Probzbility 3
D ES CP.I P T I D H : The purpose of this task is to quantify to the extent possible, the probability of design basis flood events.
Adequacy l?
P c'
of the existing deterministic method for estimating design basis k
floods is not in questi on.
s SCHEDULE: 1982 CURRENT STATUS: Unknown P
k PROBLEMS:
,__4_
TYPE FLAG
,,}lA T U L PRIORITY TA_SK A.P.
TECH. RES IMPLEMENTATIDH TACS 4 ILP_D A T EL h
31 L
ACilVE NO IHCOMPLETE 02/00/81 P
2 r
HRR G.
Staley (492-8141) HGEB/DE TITLE: Dam Failure Model DESCRIPTION: Assessment of dam failure usually requires use of P
N emperical time-failure rate models or instantaneous failure models.
1 The time failure models are unverified and the instantaneous failures model is possible unnecessarily conservative.
The issue is that pJ significant over conservatives may require otherwise unwarranted P
flood protection or execute certain sites.
4 SCHEDULE: Ho schedule.
This task provides a forum for continued r:
assessment of the issue.
CURRENT STATUS: Current State-of-the-Art has not progressed Wh sufficiently to warrant realistic assessments.
PROBLEMS:
o, fr a
e 1
f a'
.s
?
y
'i e
i N
f P
- I, J
9 4
=
u f
l f
r' SI m
m-__
._g---
- -.. _ m vu
-r HRR R. Cedill HGEB/DE
()
TITLE: Ica Effects en Safoty Ralated Watsr Supplies DESCRIPTION: Not an idsntified safaty issus.
Tha opsrating expsrienco during recant sovere winters idsntified physicals phsnom:na which might adversely impact the proper operation of safety-related systems
()
(i.e.,
the utlimate heat sink) and impair the ability to obtain sufficient cooling water to safely shut the plant down.
Typical icinq conditions (e.g.,
surface ice) appear less important than subsurface frazile ice as a flow blockage mechanism.
8%
Pack ice on packed surface ice has, in the past, been assumed sufficiently porous to pass the relatively low flows necessary for UHS operations.
Frazile ice may not be as porous and may,
'S under rare conditions, reduce the flow below acceptable levels.
The object of this task is to ensure that operating reactors have the ability to circulate warm water to the intake (or have other processes) to limit ice buildup.
SCHEDULE: Hone CURRENT STATUS: Issue serves as a forum for staff to monitor progress in the area.
PROBLEMS:
i UE #
11EE FLAG STATUi_
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED j
B-33 L
RESOLVdD NO COMPLETE COMPLETE 01/00/81 HRR Frank Congel (492-7542)
RAB/DSI TITLE: Dose Assessment Methodology DESCRIPTION: Not a safety issue.
This task involves the maintenance of calculational capabilities for assessing doses to individuals from radiation and radioactive effluents from normal operation and from radioactive releases from postulated accidents.
SCHEDULE: Complete l
CURRENT STATUS: Updated models are included in Regulatory Guido i.109 l
and are used for SEr, DES and FES sections concerned with public 4
exposure to radioactive materials and effluents.
PROBLEMS:
{
idi_8 IXEE FLAG STATUS _
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED-l B-34 L
ACTIVE YES
}
HRR D. M. Collins (492-7614) RAB/DSI TITLE: Occupational Radiation Exposure Reduction l
DESCRIPTION: This task is superceded by TMI Action Plan item III.D.3.i.
i SCHEDULE:
a 1
CURRENT STATUS:
I PROBLEMS:
6 I,
1 l
e f
k i
E_8 IfPg FLAG STATU1_
PRIORITY TASK A.P.
TECH. REi, IMPLEMENTATION TACS #
MPDAlfQ_
b
~55 L
ACTIVE YES INCOMPLETE 02/00/81 HRR Richard Bangart (402-7633)
ETSB/DSI P
TITLE Confirmstien of Appandix I Modnis for Calculations l'
of Releasss of Radicactiva Materials in G3ssous and Liouid Effluents from Light Water Sealed Huclear Power Plants DESCRIPTION: This is not an identified safety issue.
The task involves P
N rev;sion of models for calculating releases of radioactive materials to improve the accuracy of current staff models for appendix I calculations.
SCllEDUL E : Completion dependent on manpower and priorities.
No 8"
effort is beina expended at present.
CURRENT STATUS: All research programs described in the action plan have been completed except for the source term measurement program which is still underway.
NUR EG- 0 016, Rev. I was published January, 8"
1979.
HUREG-0017, Rev. 1 is in early draft stage.
PROBLEt1St Ph r
E_t IIPE FLAG
_ STATUS _
PRIORITY TASK A.P.
IECH. RES.
UPDATED _
-36 L
RESOLVED H0 COMPLETE COMPLETE 01/00/81 Q
NRR Richard Sangart (402-7633)
ETSB/DSI h
TITLE: Develop Design, Testing and Maintenance Criteria for 96 e
Atmosphere Cleanup System Air Filtration and Adsorption d
Units for Engineered Safety Feature Systems and for Hermal 3
Ventilation Systems.
y DESCRIPTIDH: Title is self explanatory, 8'
f)
SCHEDULE: Complete CURRENT STATUS: Completed - resolution is documented in Regulatory Guides 1.52. Rev. 2, dated March 1978, 1.140 Rev. I dated Oct. 1979.
H PROBLEMS:
9" j
E_#
TYPE FLAG STATUS _
PRIORITY TASK A.P.
JECH. RE}.
MPDAlfD_
i
-37 E
ACTIVE NO 1.'r0MP L E T E NOT STARTED 02/00/81 8"
4 HRR J.
C.
Lehr (492-4831)
EEB/DE TITLEt Chemical Discharges to Receiving Waters j
DESCRIPTIDH: This task will provide insight into impact of chemical discharges and provide procedures for quantifying 85 Ll impacts.
To provide a better defined division of responsibility between HRC and EPA.
4' SCHEDULE: Suspended due to lack of manpower.
CURRENT STATUS: ESRPs and Regulatory Guide 4.2 will be modified 85 g
upon completion of review of contractors work.
9 PROBLEMS: Work has been deferred because of lack of available staff.
8, 1
h i
l i
9 1
I.
P
,k E
o
L
.L.tr_s etAu s AIUL PRTURITY TAS CA.P.
TECH. RES.
JMP L EMEEIAILO_M TACS a
!!.PD A Tf D_
B-38 E
ACTIVE HO INCOMPLETE NOT STARTED 01/00/81 HRR G. E. Genra (492-4807)
EEB/DE TITLE: Rscannaissanco Level Investigstiens DESCRIPTION: This task wnuld d2volep the basis of c utaff positien providing quidanca to cpplicants concerning the need, applicability, utilization and scope of an adequate reconnaissance level investigations.
SCHEDULE: Hot available CURRENT STATUS: ESRPs, Proposed rule on alternate sites and Regulatory Guide 4.2 will be revised upon completion of review of contractors work (NUREG CR/0990).
This work is being deferred due to a
unavailability of staff.
PROBLEMS:
)( #
TYPE FLAG STATUS PRIORITY TASK A.P.
_T EC H. REit JMPLEMEHIATLQB TACS #
UPDATED _
3-39 E
ACTIVE NO IHCOMPLETE NOT STARTED 01/00/81 HRR G.
E. Gears (492-4807)
EEB/DE TITLE: Transmission Lines DESCRIPTION: This task covers HRC participation in an interagency effort 3
to set forth practices for siting and managing transmission line carriders for the betterment of wildlife.
Also, HRC will participate with other agencies to develop a single environmental review process involving all transmission systems of joint concern.
SCHEDULE: Work has been suspended due to unavailability of staff.
[
CURRENT STATUS: ESRPs and Regulatory Guide 4.2 will be revised upon completion of review of contractor's work (FWS/0BS-79/22).
PROBLEMS:
m O
i en v
()
1
-~
~
=,,
7 ~
,..rc
,, n.
x.- -
O bg
]dQb( U ELQBR_
PRIIiRI9Y ~ TASK 0.P.
Tg@H. R EL.
IMPLEdgNIATIDH TACS #
UPDATED _
l-40 E
DIKCTIV E NO INCOMFLETE HOT STARTED 01/ 0 D/81 HRR C. R. Hickcy (492-4677)
EEB/DE C>
TITLE: Effects of Pcw:r Plant Entrainm:nt on Plenkten g
~
DESCRIPTION: Th2 effects of untrainmant en phyto-End zooplankton i
populations cra etan minimal and ocr.asionally beneficial.
Numerous
[
studies of the effects of entrainment on plankton organisms, f*
phytoplankton and zooplankton, have shown impacts to be minimal and/or not significant.
Studies have also shown that even wSen entrainment mortaility is high, the overall impacts may be minimal due to the fast reproductive and recovery time for many pecies - a few hours for some phytoplankters to several days for zooplankton.
Utilities have undertaken exhaustive and sometimes unnecessary preoperational and operational environmental monitoring programs.
P In view of the above points, it may be possible to reduce or climinate studies of certain planktonic elem9nts, perhaps on a i
site or regional basis.
A study of these matters will form the basis for a staff position on monitoring requirements of plankton f*
and entrainment programs.
If the state-of-the-art as defined in g
j the study is adequate, perhaps intensive studies can be reduced, saving time and nxpense for both utilities and the NRC staff.
SCHEDULE: Not scheduled P
CURRENT STATUS: Hothing has been done on this item due to insufficient I
manpower.
PROBLEMS:
O s
r JL R TYPE FLAG
_ STATUS _
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS 8 UPDATED l
.-41 E
INACTIVE NO IHCOMPLETE NOT SIARTED 01/00/81 HRR Mike Masnik (492-4820)
EEB/DE P
DESCR PT ON Th s olves studies related to the impacts of power plant operation on fishery resources, for a description of studies see HUREG-0471, pg. B-52.
P
)
SCHEDULE: Suspended until manpower becomes available, CURRENT STATUS: ESRPs and Reg. Guide 4.2 will be modified upon j
completion of review of contractors report.
j PROBLEMS:
P l
t JL 8 TYPE FLAG
_ STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED _
-42 E
ACTIVE NO 02/00/81 P
HRR Donald P.
Cleary (492-4875)
SAB/DE f
TITLE: Socioeconomic Environmental Impacts l
DESCRIPTIDH: As part of the cast benefit analysis for plant licensing, I
HRC is required to assess likely socioeconomic impacts of plant P
I construction and operation on local communities and the surrounding region.
This task is designed to improve the ability to forecast impacts for use in preparing environmental statements and hearing i
testimony.
P j
SCHEDULE: Unknown CURRENT STATUS: Continuing at a very low level of effort.
,I PROBLEMS:
}
f
\\
2 f
w-30
1_aum-- gg Mga4Ra 11 0 0
dls!-N
A S
-- ' Jamwoon(
HRR G. LaRocho (492-4821)
EEB/DE
()
TITLE: Valua of Asrial Photographs for Site Evaluatien DESCRIPTION: Tho technique of aarial photography has a long establish:d and provan utility for earth resource inventory and evaluation.
Applicants for nuclear construction permits are becoming aware of f) this and are making increasing use of aerial photographs in their environmental reports.
The uncertainties with the methodology at present relate tos (1) photo interpretation techniques and the 4
extent to which existing regulatory quidance can be mot using P% ' j this method; (2) fine tuning of the interplay between aerial o
photography and ground truthing needed to meet licensing requirements; (3) quantification of presumed cost advantages of this method; and (4) relative information return from different
'T films, photographic scales and seasens of coverage.
This task
?
will examine existing regulatory guidance and produce a list of items which might be fulfilled in whole or in part from aerial photographic information.
Field tests on actual sites will be 6
carried out to determine the information return from photographs in relation to regulatory requirements and in relation to I
conventional ground based data collection efforts.
The results will give the staff a documentary basis for accepting a:*ial photographic inventories and resource evaluation in environmental reports and for revising existing guidance for making environmental surveys.
SCHEDULE: Hot available CURRENT STATUS: A research request for proposal is being developed.
PROBLEMS:
UE e TYPE FLAG STATUi_
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATER _
B-44 E
ACTIVE NO 01/00/88 HRR Darrel Hash (492-9882)
UFB/DE TITLE: Forecasts of Generating Costs of Coal and Huclear Plants DESCRIPTIDH2 In the performance of HEPA obligations to evaluate alternatives to the proposed action, the staff must reach a conclusion as to the comparative costs of generating power among the feasible alternatives.
While alternatives other than coal are treated in the staff's analysis, coal represents by far the most feasible alternative and requires detailed cost comparisons equivalent to those performed for nuclear.
For the several years, the staff has used a computer code known as CONCEPT to obtain forecasts of plant capital costs.
This code was developed by ORHL based upon design specifications and cost estimates done by United Engineers and Constructors.
This task involves maintaining and I
developing improvements to the COHCEPT code so that it remains up-to-date for use in projections of power plant capital cost, front-end cost and generating cost forecasts.
SCHEDULE: Completion ate FY-82 CURRENT STATUS: Model is being changed to reflect cost of incorporating TMI changes in plants to be constructed.
Studies are being done to improve estimates of scale economices by increasing the size of coal and nuclear plants.
PROBLEMS:
i t
FLAG PRIORITY TAS A.P.
P E A
3 TACS #
UPDATED HRR Sidnay Fsid UFB/DE
()
y TITLE:
Hand for Powsr - Enargy Censsrvrtien I,
DESCRIPTION: This task has bnen includsd as part of B-2.
G SCHEDULE: See task B-2.
CURRENT STATUS: See task B-2.
PROBLEMS:
h 0
uj!
TYPE FLAG STATUS ERIORITY IASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED
- 5
(
46 E
HRR TITLE:
Cost of Alternatives in Environmental Design DESCRIPTIDH: Frequently regulatory changes are made in the applicant's dm proposal for design and/or operation of systems or subsystems based L,
on perceived needs to mitigate impacts on the environment.
- Also, differences in design and/or operation are an integral part of the
~
treatment of alternatives in the EIS.
The cost of such chances or
- b alternatives, if calculated, are determined on an ad hoc basis.
1 However, this cost is not always calculated, and many times they
'{
are not calculated on a consistent basis.
A more consistent and il comprehensive analysis of the cost of various design and operating F
j modes appears to be warranted so that there is a reasonable and pj docunerited rationale for determining such costs.
Such costs would a
also have to include costs of redesign.
Once experience is gained
- I in this area, consideration would be given to expanding the study 95
'l to the cost of making changes because of changing safety criteria, both from a redesign standpoint as well as from a "backfit" point
)
of view.
U' SCHEDULE: Unknown P
~.
CURRENT STATUS: Unknown 9
PROBLEMS:
,I L.
-[
P t
,U 9
0 P
pb ci 11 P
l i'
\\
f>'
h
t,w jf_ s. TYPE FLAG STAVUS__
PRIORITY TASK A.P.
TECH. RES2 IMPLEMENTATION TACS #
UPDATED B-47
,5 ACTIVE NO INCOMPLETE NOT STARTED 01/00/81 NRR Dave Sellers (492-9493) MTEB/DE TITLE:
Inservice Inspection Criteria for Supports and Bolting of Class 1,
2, and 3 and MC Components DESCRIPTION: This task is partially covered by USI-A-12 " Fracture Ph Toughness of Steam Generation and Reactor Coolant Pump Supports".
The original task description as published in NUREG-0371 is as follows:
Results from inspections of various structural components in the torus support systems of operating Di!Rs have indicated soveral I'
inconsistencies between the design drawings and the "as built" hardware, including missing support struts, out of tolerance weld dimensions, unwalded regions and unsupported columns.
In addition, a limited number of separate inspections have been performed on PWR steam
- T generator supports.
The results of these inspections revealed several cracked support bolts.
In view of the above, additional investigation of BWR and PWR
'T component support systems should be undertaken to determine if similar deficiencies and "off design" conditons exist eenerally in operating plants.
This investigation should determine the extent of support system deficiencies, and whether the deficiencies are service induced or are the result of faulty construction.
Determination of the extend and nature of the deficiencies is necessary to define the possible safety significance and to provide guidance for further appropriate staff action regarding inservice inspection of supports.
SCHEDULE: Unknown CURRENT STATUS: Draft standard review plan for fracture toughness control of component supports does not allow dependence on ISI for component support integrity.
PROBLEMS:
^T
=
T e~
m)
T$PI FLAG
_SVATUS PRIORITY TASK A.P.
TECH. RES.
IMPl.EMENIATION TACS 8 MP_DATEQ_
48 S
RESOLVED H0 COMPLETE IN PROGRESS 01/00/81 Lj dP h+
HRR Warren Hazelton (492-7352) MTEB/DE TITLE:
BWR CRD Mechanical Failure (Collet Housing)
DESCRIPTION: Surface cracks have been discovered in control rod h..
I drive internal parts at some operating BWR plants.
This cracking, Sk
["
f although only observed to be localized in nature, if propogated could potentially affect the capability of the control rod drive I
fl:
to perform its design function.
Cracking has been identified in the following control red drive internal parts:
the collet retaining P
]
tube (CRT), the posion tube, and the index tube.
J The cracking in the collet retaining tubes was located near a transition in tube thickness approximately six inches down the tube.
IP The cracks appear to have initiated on the outer tube surface and cU to have propogated circumferential1y in the areas between the flow k
holes of the tube.
The cracking in the index and piston tubes E.
have occurred in the creviced, sensitized and non-nitrided threaded WD areas of these tubes.
L The extent of the cracking observed at operating BWR plants to date has not been severe enough to impair the ability of the control rod d>
drives to operate in their required capacity.
As an interim precautionary measure, additional technical specification requirements q
worn established for operating reactors which require shutdown within 6
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> r f detecting a rod unless investigation demonstrates that dP
,?
the cause of the failure was not due to a separated collet tube.
Another technical specification that has long been in effect for operating reactors requires exercising fully or partially withdrawn f
rods once every week as a part of the corrosion prevention program.
f>
This recuirement also provides demonstration of CRT integrity, y
SCHEDULE: Implementation schedule not available I
CURRENT STATUS: General Electric is replacinq old style surface hardened colletts with new non-surface hardened colletts.
P 3
PROBLEMS:
- l1 k
p g
a 1
'1 0
k a
P 1
$n f
a c
l JL 8 lYPg FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED L-4 9 L
HD
(~%
j TITLE:
Inservica Inspzetien Critcria end Csrrosien Preventien Criteria for Containments I
DESCRIPTION: General Design Criterion 53, " Provisions for Containment Testing and Inspection," requires in part that the reactor containment l}
t I
be designed to permit:
(1) periodic inspection of all important areas, and (2) an appropriate surveillance program.
" Primary Reactor Containment Leakage Testing for Water-Cooled Power Ph l
Reactors," requires a general inspection of the surfaces of the containment prior to any Type A test to uncover any evidence of structural deterioration.
J
'5 Containment designs typically utilize any one of the following b
structural materials:
steel, steel lined reinforced concrete, steel lined prestressed concrete.
To date the only detailed criteria that h
have been developed for inservice inspection of containments relate i
to tendon surveillance for pre stressed concrete containments.
These criteria are contained in Regulatory Guides 1.35 and 1.90 which address ungrouted and grouted tendons respectively.
These Regulatory Guides deal primarily with the pre-stressing hardware; no detailed inservice inspection criteria exist for the steel liner or other portions of the containment.
Similarly, there are no criteria for inservice inspection of steel containments or steel lined reinforced concrete containments.
In view of this, detailed and comprehensive criteria need to be developed for performing inservice inspections of all type of containments.
In addition, the long term corrosion problems of reinforcements and of the steel liner in contact with concrete in concrete containments, j
the corrosion of the steel surface in contact with the water in or BWR suppression chambers, have yet to be adequately analyzed.
Long term studies of these corrosion phenomena need to be undertaken to develop criteria and requirements to prevent corrosion in all types of containments.
SCHEDULE: Unknown CURRENT STATUS: Unknown PROBLEMS:
6 I
~
f I
I
- )
ein.
g, e
e m
w y
w w
ee e
e 4
ea e s-c'
-m=9 e
gee e
p dk
_y I
C) y
~
i UE 8
- TYPF, FLAG
_ STATUS _
PRIORITY TASK A.P.
IfCH. R gi, JMPLEMENIAllqN TACS #
UPDATED B-58 L
IHACTIVE NO IHCOnPLEIE HOT STARTED 01/00/81 8P HRR 0.
Rothberg (492-9566)
SED /DE TITLE:
Post Operating Basis Earthquake Inspection
{
DESCRIPTIDH: Section V9a)(2) of Appendix A to 10 CFR Part 100 states i
f that licensees will be required to shut down their plants in the event i
of an earthquake if vibratory ground motion exceeds that of the OBE.
80 f
Prior to restart the licensee must demonstrate to the NRC that no functional danage has occurred to those features necessary for continued operation without undue risk to the health and safety 8"
of the public.
In order to datermine the capability of a plant to resume operation following an OBE an adequate inspection of the plant and site area must be performed.
The requirements for this post-0BE inspection are stated in Section 3.7.4.ii.4 of the Standard 8'
Review Plan.
Since neither the Regulations nor the Standard Review Plan provide details on the extent of such inspections, this task will develop an acceptable inspection procedure.
SCHEDULE: Unknown 85 CURRENT STATUS: Unknown PROBLEMS:
WE #
11Eg FLAG STATUS PRIORITY TASK A.P.
IECBi_ Ritz 1MPLEMENTATION TACS 4 MPDATED P
-51 L
ACTIVE NO INCOMPLETE HOI STAR 1ED 01/00/81 HRR M. Hartzman (492-9478) MED/DE TITLE:
Assessment of Inelastic Analysis Techniques for 8"
Equipment and Components DESCRIPTION: In the design of nuclear power plants, inelastic response of equipment and components due to severe transients from low probability events is permitted in the ASME Boiler and Pressure Vessel d'
Code,Section III, Subsection HA, Appendix F.
Local inelastic response is also permitted for structures under severe impact loads due to low probability events.
l 8"
Assessment of inelastic analysis techniques applicable to equipment I
I and components is the basic objective of this task.
Inelastic l
analysis techniques for structures are under study as a part of HRR I
Category A Task No. A-40, " Seismic Design Criteria - Short Term 8'
Program."
Since inelastic analysis procedures acceptable under Appendix F of the ASME Boiler and Pressure Vessel Code permit Level D Service
)
8B J
Limits and since Level D Service Limits allow large inelastic i
strains, it is particularly important that properly qualified analysis techniques are ured, and that their limitations are properly understood.
SCHEDULE: No firm schedule (FY-1982) 8" CURRENT STATUS: Work is progressing under contract with Brookhaven National Laboratory.
PROBLEMS:
}
e 9
e
(I JE 8. TYPE FLAq_
STATUi_
PRIORITY TASK A.P.
TECH. B Ei.
IUPLEMENIATION TACS #
MERAlfh_
B-52 USI RESOLVED YES COMPLETE IH PROGRESS 05/00/81 HRQ Jim Shea (492-7231)
ORB 2/DL
($
TITLE:
Fuel Assembly Scismic and LOCA Responses 1
DESCRIPTION: The fuel assembly is a highly nonlinear structure which can
' l be subjected to substantial loadings during seismic excitations and LOCA transients.
The integrity of this assembly is critical for plant yi w
j safety.
Extensive work has been completed by HSSS vendors for the determination of fuel element response during the sustained vibrations lg of normal operation.
However, there is a need to study the behavior of these assemblies during accident conditions.
Future work will E,)
include a determination as to whether or not existing geometry can adequately satisfy the functional design criteria.
Vibration interaction between components of the assembly and reactor pressure 8
vessel will be investigated.
Subsequent to its approval as a Category B task, this task has been included within the scope of Task A-2, Asymmetric Blowdown Loads on PWR Primary Coolant Systems.
SCHEDULE: See AQUA Book, HUREG-0600 for implementation schedule and status.
CURRENT STATUS:
PROBLEMS:
/E #
TYPE FLAG
_ STATUS _
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED l-53 S
ACTIVE HO INCOMPLETE IN PROGRESS 01/00/81 HRR J. Lazernick (492-7773) PSB/DSI TITLE:
Load Break Switch DESCRIPTION: Plant designs which utilize generator load circuit breakers to satisfy the requirement for an immediate access circuit s'.ated in GDC-17 must be prototype tested to demonstrate functional caoability.
This task involves the preparation of a staff position to claeify and document the prototype testing requirements for generator load circuit breakers and associated circuitry used to provide an immediate access circuit in accordance with GDC-17.
This technical position, when conpleted, will be incorporated in the Standard Review Plan.
SCHEDULE: Completion mid 1981 CURRENT STATUS: Hot applicable to operating reactors.
The first appilcable plant was ricGuire and the issue resolved on this docket.
Other OLs will be handled the same way.
A Branch Technical position is being written which will be incorporated into SRP 8.2.
l PROBLEMS:
O 4
d
[
ap
s f
IE 3 TIPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED._
(
P54 5
F HRR C. Tinkler (492-9421)
CSB/DSI l
TITLE:
Ice Condenser Containments DESCRIPTIDH: This task involves two staff efforts associated with the ice condenser containment concept.
9 e'
(1) Verification of the established design margin for ice condenser containments to the satisfaction of the ACRS, and I
(2) Reviewing the surveillance programs for ice inventory and functional performance testing at operating facilities to determine whether the surveillance frequencies should be increased or other action should be taken.
Operating experience from the D. C. Cook P
{
plant has indicated that sublimation and ice melting are causing 1
loss of ice inventory and related functional performance problems.
a SCHEDULE: Unknown CURRENT STATUS: Unknown P
PROBLEMS:
I 9
^
9 I
1 e
- l 9
e t
4h,
'UE #
TYPE FLAG STATUS PRIORITY TASK A.P.
JECH. RES IMP (EMENIAJION TACS #
MPDATfD_
1 9-55
,S ACilVE NO INCOMPLETE IN PROGRESS 01/00/88 NRR F. Charny (492-9472) MEB/DE
()
TITLE:
Improved Reliability of Target Rock Safety-Relief Valves DESCRIPTION: Target rock power operated relief valves are used to limit the pressure rise in boiling water reactor (BWR) transients and to automatically depressurize the primary system in the event of certain 4D loss of-coolant accidents.
In the past, a significant number of Target Rock power operated relief valves installed in BWRs inadvertently opened and subsequently failed to rescat until the primary system was essentially depressurized.
The primary cause of valve GD maloperation was due to erosion of the setpoint pilot valve seat, resulting in the leakage of steam into the second and third stages of the valve actuator.
There is a strong correlation between pilot y
i leakage and the amount of " simmer margin" (SRV setpoint pressure GP minus systen operating pressure) for the valve.
Virtually all of the SRV blowdowns occurred on valves with less than 100 psi " simmer margin."
For the short term, General Electric (GE) proposed that licensees (1) grind out the throat diameters of Target Rock SRVs 4D which will allow the valve setpoint to be raised 35 psi and (2) monitor SRV tailpipe temperatures (from existing thermocouples) l to detect valve leakage prior to an inadvertent actuation.
For
'j the long-term, GE (in conjunction with Target Rock) has proposed 49 a redesigned valve actuator for Target Rock SRVs.
The most significant change would be the elimination of the second stage so that any leakage past the pilot would exhaust rather than cause a pressure buildup to the actuating pressure in the second et stage.
GE and Target Rock have manufactured for prototype valves with this modification and have begun a testing program.
This task involves monitoring the current pr grams and developing generic positions for use in the review of individual plants.
et SCHEDULE: Schedule for implementation not established.
CURRENT STATU3: General Electric (at suggestion of HRC) has developed a three pronged approach to improving target rock reliability.
9 (1) Replace 3 stage target rock valve with an improved 2 stage 1
design - about 2/3 have been replaced.
I (2) Increase the simmer margin on operating plants which have three stage valves.
4>
(3) Discontinue use of target rock valves on new plants (most are Mark IIs and IIIs).
There is some data from last 2 or 3 years of BWR operation to Gk show that inadvertant blowdown frequency has decreased.
- ifowever, there have been some additional problems with the new two stage valve which were addressed in a recent IE Bulletin.
There is very little data available on other SRVs to be used on Mark IIs 9'
i and IIIs.
I PROBLEMS:
l t'
J
I T.A_S K A.
IECH. R FJ_,.
JMLEt!Et4T ATIJN TACS #
L!PJ A_IED_
A L_8 TYPE FLAG
_ STATUS _
PRIORITY
-5b S
RESOLVED HO C0til'L E T E HOT STARTED 04/00/81 O
HRR Al Ungaro (492-5024) PSB/DSI TITLE:
Dios:1 Raliability DESCRIPTION: An cximinatien of Licens03 Evsnt Rapsrts en tha expsrienco with diesel generators (1969-1975) indicates that the emergency onsite diesel oenerators at operating plant have an average reliability of 9"
about 0.94 compared with the HRC's reliability goal of 0.99.
The reliability of the diesel generator is strongly dependent on the interaction of the following factors:
design, testing and operational requirements, operational history, inspections, maintenance, and the Sk k
personnel qualification of operators.
The lack of detail regarding the failures reported in the Licensee F
Event Reports make it difficult for the HRC to establish the causes of the reported failures.
A comprehensive review to determine the underlying and recurring causes of the reported failures is necessary I
in order to enable the HRC to establish improved guidance and requirements to increase the reliability fo the emergency onsite diesel 9'
generators.
SCHEDULE: Schedule not established i
CURRENT STATUS: Generic letter has been written and transmitted to L
9 I
Division of Licensing for implementation.
PROBLEMS:
E_t TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED P
=57 USl NRR Pat Baranawski (492-5921)
PAS /RES j
TITLE:
Station Blackout 3
DESCRIPTIDH: This task is part of USI A-44, " Station Blackout" P
S CilEDU L E : See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606
-f PROBLEMS:
E#
TYPE FLAG _
STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATIqH TACS #
UPDATED -
-58 S
NO HRR TITLE:
Passive Mechanical Failures DESCRIPTION: This task involves a review of valve failure data in a
+
more systematic manner to confirm the staff's present judgment regarding the likelihood of passive mechanical valve failures, P
catcoorize these and other valve failures as to expected frequency, specify acceptance criteria and determine if and how the results j
a of this effort should be applied in licensing reviews, P
SCHEDULE: None CURRENT STATUS: Hot available PROBLEMS:
[
P i
f I
F h
f 1
E_t TYPE FLAA_
STATUi_
PRIORITY TASK A.P.
IECH, RIS, IMPLEMENTATION TACS #
UPDATED
+59
.5 AC T IV E YES INCOMPLETE f'
I HRR Tom Loomis (492-9403) RSB/DSI 1
TITLE: Review of (H-1) Loop Operation in BWRs and PWRs t"
DESCRIPTIDH: The majority of operating BWRs and FWRs are designed to I
operate with less than full reactor coolant flow.
If a PWR reactor i
coolant pump or a BWR recirculation pump becomes inoperative, the flow provided by the reamining (N-1) loops is sufficient for steady il state operation at a power level less than full power.
Although FSARs for the licensed Bt!Rs and PWRs present (H-1) loop calculations showing allowable pouer and protective system trip setpoints, the
'I staff has disallowed this mode of operation for most plants primarily due to insufficient ECCS analyses.
Some Babcock 8 Wilcox (B8W)
L; PWRs are authorized for long term operation with one reactor coolant O
pump out of service since they have submitted and the staff has approved the necessary ECCS, steady state, and transient calculations.
f'
~
The re.naining BWR and PWR licensees have Technical Specifications which require shutdown within a fairly short time if one of the O
P reactor coolant loops becomes inoperable.
The purpose of this task is to develop a set of acceptance criteria t
and review guidelines for the (N-1) loop authorization requests.
O SCHEDULE: Hot established CURRENT STATUS: All B8W plants have been approved for H-1 operation.
Contractor reports on Westinghouse plants H-1 operation are under staff review.
Combustion Engineering has submitted analyses for O
d Calvert Cliffs.
The review of BWRs has been suspended pending j
review of the incident at Browns Ferry when core vibrations occurred during single loop operation.
A meeting is scheduled with a GE owners group to discuss the incident.
l
(
l PROBLEMS:
L
)
13 9'
N f
- 1 4
an t
\\
- 3 e
1, h
+.'
~
" lf F
LJ TXPg FLAG STATU_i_
PRIORITY TASK A.P.
TECH. RElm IMPLhMENTATION TACS.? N UPDATED 0
"60 S
R ESO Li/ ED x
H0 CottPLETE C0f1PLEIE 05/00/81 s
f.
C) l' NRR G. Weidenhammer'(443-5997) MiEB/RES' TITLE:
Loose Parts Monitoring System DESCRIPTION: The presence of a loose (i.e.,
dicongaged and/or drifting),
hj
&bject in the primary coolant systec can be lndicative of degraded
[
F reactor safety resulting from failure or weakenirl'of a safety-related-C c o mp o n e r. t.
A loose part, whether ithhe from a falled or weakened component or frcm an item inadvertently left in the primary system t
5 during construction, refueling, or maintenance procedures, can contribute to component damage and material wear by frequent P
l impacting with other parts in the system.
A loose part can pose a serious threat of partial finw blockage with attendant departure
'from nucleate boiling (DNB) which in turn could result in failure I
+
of fuel cladding.
In addition, a loose part increases the potential
/'
for control rod jamming and for accumulation of increased levels o f.
radioactive crud in the primary system.
The primary purpose of the loose - part detection program is the P
(
carly detection of loose metallic parts in the primary system.
Early dotection can provide the time required to avoid or mitigate y
safety related damage ta or malfunction of primary system components, y,
9 a
The purpose of this task is to resolve any outstanding issues related L
to the-proposed Regulatory Guide, including the development of staff d
positions and guidance with respect to upgrading loose parts detection q
systems at operating facilities.
O.
J1 SCHEDULE: N/A CURRENT STATUS: All cps and Ots under review after 1/1/78 were required j
^
to meet privisions of RG 1.133.
CP and OL applicants after 1/1/78 p
are required to review their systems and determine if they comply P
or are equivalent.
See implementation section of RG 1.133 for
,g details.
,f PROBLEMS:
- l P
M P:
1 9
4 3
1N 9
1 a
P 1
h r
1 9
a
')
d b.
't k
O 3#E_ #
TYPE FLAG
_STATUi_
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED _
B S INACTIVE H0 COMPLETE 05/00/81 HRR Carl Esrlinazr (492-8414)
SEP/DL Ib TITLE:
Allowablo ECCS Equipment Outage Periods DESCRIPTIDH: Surveillance test intervals and allowable equipment outage periods in the Technical Specifications for safety related systems are largely based on engineering judgement.
Analytically d>
based criteria are needed for the staff's use in confirming or modifying these surveillance intervals and allowable equipment outage periods.
SCHEDULE: Hot scheduled UD CURRENT STATUS: Initial work on methodology for optimizinq survnillance intevals was performed under contract with SAI.
This phase of the task was completed and four reports issued.
1.
"The Impact of Component Outages on ECCS Unavailability" d>
dated August 1975 report no. SAI-75-550-HA.
2.
" Amendment to " Impact of Component Outages on ECCS Unavailability" Based on HRC Surry Power Plant ECCS Analysis" II dated May 1976, report no. SAI-76-536-WA.
3.
'The Impact of Component Outages on ECCS/ECI Unavailability for an Operational Resar-3 PWR" dated July 1977, report no.
db SAI-76-622-WA.
4 "A Quantitative Approach for Establishing LCOs for ECCS/ECI Components" dated March 1979, report no. SAI-78-649-HA.
d>
An RFP and Task description was prepared and issued in early 1978.
Following TMI the RFP was recalled and no further action has been taken on this task since then.
There is currently no activity.
ab PROBLENS:
LUE 4 TYPE FLAG STATUS PRIORITY TASK A.P.
IECH. RES.
IMPLEMENTATION TACS #
UPDATED O
B-62 L
RESOLVED H0 COMPLETE HRR Lan Fleno (492-7579)
CPB/DSI TITLE:
Reexamination of Technical Bases for Establishing SLs LSSS.
db DESCRIPTIDH: The methods used to establish safe operating limits for reactor cores were developed about ten years ago.
At present, safety margins are reviewed utilizing previous staff judgements i
based on individual plant reviews.
A uniform staff position noods db to be developed for application to core performance reviews of new plants and to reloads and core modifications of operating plants.
SCHEDULE:
CURRENT STATUS: This is not a safety issue.
There is no activity Ib I
in this area, nor is there any planned.
PROBLEMS:
an I
e i
e I
--- *O
SUE R M
FLAG STATUS PRIORITY TASK A.P.
TECH. R E.S JfMtigNTAT10]i TACS #
MPDAT_ED S
B-63 S
RESOLVED NO COMPLETE IN PROGRESS 05/00/81 2
HR2 A.
Cappuci (492-9476) MEB/DE C*
TITLE:
Isolation of Lew Pres:ura Systama Cennscted to the Reactor Coolant Pressure Boundary DESCRIPTION: There are several systems connected to the reactor coolant pressure boundary that have design pressures that are considerably
@~
below the reactor coolant system operating pressure.
The HRC staff has required that valves forming the interface between these high and low pressure systems have sufficient redundancy to assure that the low pressure systems are not subjected to pressures which exceed their design limits.
Recently, there has been discussion relative to the adequacy of the isolation of low pressure systems that are connected to the reactor coolant pressure boundary.
Past reviews have concentrated on insuring isolation of the residual heat removal system, which is a low pressure system on almost all PWRs and BURS.
Current reviews of license applications for new plants, that is, our CP/0L evaluations, are based on guidelines set forth in the Standard Review Plan (SRP).
However, these guidelines were not available during the reviews of the plants which are currently operating.
SCHEDULE: Hot established CURRENT STATUS: An order was issued to all operating reactors in April 1981 to comply with requirements of technical resolution for event V configurations.
All other configurations are being addressed by inservice testing SERs and are being issued as license amendments.
9" Resolution is documented in Appendix A to Standard Review Plan
3.9.6. PROBLEMS
i i
I I
e f
f
\\
9-f' f'
F O
9 iUg e
- TIPE FLAG STATU1_
POIO7ITY TASK A.P.
IfCH. Rfi.
IMPifMENTATION TACS #
UPDATEQ_
B-64 ACTIVE NO INCOMPLETE IN PROGRESS 05/00/81 HRR PHIL MATTHEWS (492-8301)
CEB/DE C?
TITLE:
Decommissioning of Reactors DESCPIPTION: Establish guidance and acceptance criteria for the Decommissioning of Reactors needs to be developed to update Reg Guide 1.86.
A more detailed description is included in HUREG-0471 dated d>
June 1978.
SCHEDULE: See Current Status CURRENT STATUS: 1 Regulatory Requirements / Guidance The staff requirements and guidance for nuclear plant and fuel cycle IP facility decommissioning are undergoing extensive review and revision by the Office of Research and Standards.
The major milestones in this program are:
O
- 1) Draft Generic EIS - HUREG-0586, issued 1/81
- 2) Decommissioning Policy Statement - targeted for transmittal to Commission 6/30/82
- 3) Proposed Rule Change - March, 1982 db
- 4) Final Generic EIS - March, 1982
- 5) Final Rule Change - March, 1983 In addition, PHL/HUREG reports have been issued which deal with the dD technology, safety, and costs of decommissioning reference nuclear facilities; e.g.
PWR's (NUREG/CR 0130),
BWR's (HUREG-0672).
- Also, the Office of Research and Standards has three research projects in support of this rulemaking effort; namely, 1) Decontamination dD as a Precursor to Decommissioning, 2) long lived activation products in reactor materials, 3) Characterization of radionuclide contaimination throughout LWR pwer stations.
O Currently, the staff conducts its review of proposed decommissioning of specific plants on a case by case basis using existing applicable regulatory requirements and guidance supplemented by applicable HUREG reports on reference facilities as discussed above.
The existing d>
regulatory requirements and guidance documents are:
- 1) 10 CFR 50.82 - Applications for termination of licenses
" Termination of Operating Licenses d>
for Nuclear Reactors"
- 3) Regulatory Guide 8.8 "Information Relevant to ensuring that Occupational Radiation Exposures at nuclear power will be as low l
as reasonably achievable (ALARA)
II l
One of the major technical issues tc be resolved is that of l
establishing uniform acceptable residual radioactivity levels of activated materials for unrestricted facility release.
Regulatory GP j Guide 1.86 only provides guidance for acceptable levels of residual surface radioactive contamination.
HRR and HMSS are working j
closely.
PROBLEMS:
Ud i
i h
9 9
n
pr
$$~ _#
TYPE FLAG STATUS PRIORITY TASK.A.P.
TECH. R E1.
IMPLEMENTATIDH TACS #
UPDATED B-65 S
HQ 9
TITLE:
Iodine Spiking DESCRIPTION: The calculated radiological consequences for some postulated design basis accidents are highly dependent on the magnitude of the P
iodine sotke postulated to occur following the transient.
These calculations in turn determine the coolant activity limits allowed in the technical specifications.
This task will develop and confirm a model for the iodine spikine phenomena.
Procurement of data from
{
f*
operating plants and the development of a fuel release model for 4
predicting the magnitude of the spikes will provide an understanding
{
i of this phenomenon which is not presently available.
Improved f
knowledge of this topic will allow setting of the coolant activity f'
i limits at realistic levels.
In addition, this could provide the basis for more realistic accident calculations.
]
SCllEDUL E : Unknown CURRENT STATUS: Unknown P'
PROBLEMS:
j 1
LUE #
TYPE FLAG
_SIAlQS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED P'
'B-66 S
RESOLVED HRR R. W. Houston (492-7323)
AEB/DE TITLE:
Control Room Infiltration Measurements l
DESCRIPTION: A key parameter affecting control room habitability under the I
conditions described in General Design Criteria 19 and Standard Review P'
l Plan 6.4 is the magnitude of control room air infiltration rates.
l Current estimates of these rates are based on data relating to buildings l
that are substantially different then typical nuclear power plant control P
room buildings.
Additional experimentally measured air exchange rates l
of operating reactor control rooms are needed to develop an improved data base.
This task will support the following requirements:
F Criterion 19 of Appendix A to 10 CFR Part 50 (General Design Criteria for Nuclear Power Plants) requires that control rooms be accessable and habitable under both normal and accident conditions.
P Safety Standard Review Plan 6.4 Habitability Systems and SRP 9.4.1 Control Room Area Ventilation Systems specify a review of the control room habitability systams with respect to the functional performance required to maintain a habitable control room area in the event of P
postulated accidents.
SCHEDULE: Unknown CURRENT STATUS: Unknown PROBLEMS:
9' F
F P
(J E #
TYPE FLAG
__STATU3_
PRIORITY IASK A.P.
IECB. RES IMPLEMENTATION TACS #
UPDATED __
t B-67
- S INACTIVE YES INCOMPLETE NRR Richard Bangart (492-7633)
ETSB/DE C3 TITLE:
Effluent and Process Monitoring Instrumentation DESCRIPTION: flonitoring of radioactivity in caseous and liquid effluent h
streams from nuclear power plants is required for several purposes:
i (a) assnssment of the adequacy of process and waste treatment systems, f>
J (b) the control of releases of radioactivity to the environment so that they do not exceed the limits of 10 CFR 20 and 10 CFR 50, Appendix I, and (c) the evaluation of environmental impact.
This task involves 6
improving current guidance to applicants and reviewer.s in the areas 4>
of radiation monitoring for process and effluent systems and reviewing the effluent monitoring systems for selected operating BWRc and FWRs to determine their effectiveness in meeting the effluent release limits of 10 CFR Parts 20 and 50.
Ib SCHEDULE: Not scheduled no one is currently assigned to task.
1 CURRENT STATUS: Study on BWR offgas explosions is complete.
No other work has been started.
PROBLEMS:
4D JE #
TYPE FLAG
_gTATUS PRIORITY TASK A.P.
IRCH. RESz IMPLEMENTATION TACS #
MPDAlgD_
3-68 5
INACTIVE NO INCOMPLETE 05/00/81
(>
HRR TITLE:
Pump Overspeed During LOCA DESCRIPTION: There is a potential for BWR recirculation pumps or PWR main coolant pumps to overspeed during a LOCA, resulting in the potential GP for missile generation.
This task involves the conduct of analytical and experimental work to determine whether or not destructive overspeeds could be attained and to determine if corrective actions are necessary.
SCHEDULE: Unscheduled d>
CURRENT STATUS: Work has stopped on this task and nothing is planned.
Each NSSS vendor has supplied reports.
They were under review for several years by the reactor Systems Branch.
A series of audit calculations were being performed at the time of thq TMI accident.
GD There has been no work since that time.
PROBLEMS:
e 4>
O 9
9 GP O
)
D R 4 h-(_6 9 TXPf FLAG STATUS _
PRIORITY TASK A.P.
TECH. OES.
IMPLEMENTATION TACS 8 UPDATED 5
RESOLVED H0 COMPLETE COMPLETE P
TITLE:
ECCS Leakage Ex-containment DESCRIPTION: Following a plant transient, or accident, provisions aro required for long term decay heat removal.
Redundance of components is required as necessary to assure that a failure in the residual hwat P
removal (RHR) system will not impair the ability to maintain the plant in a safe shutdown condition.
Should such a failure involve leakage of primary coolant (as might result, for example, in the event of a pump seal failure), the potential exists for a release of radioactivity P
to the environment.
Any resultant airborne releases are typically controlled either by provisions for filtration of airborne activity or location of RHR equipment within leaktight cells.
Contaminated liquid releases (primary coolant not volatilized when leaked) is f*
typically collected in a sump for subsequent transfer and cicanup through the raduaste system.
Some guidance is provided in various standard review plans for identifying and controlling leakage from RHR equipment (cf. SRP 6.3.3, 9.3.3, 11.2, 10.6,5, and App B).
F*
{
However, there are no specific provisions to assure that the interface g
requirements for equipment and procedures are adequately developed, g
f For example, a seal failure might result in leakage of tens of P
gallons per m;nute of primary coolant.
Any leaked fluid cannot be pumped to radwaste storage tanks unless storage capability is available.
Post-event recovery operations require knowledge of the levels of airborne radioactivity and the degree of contamination of P'
primary coolant.
Accordingly, radiation monitoring equipment must j
be suitably located to provide operators with information needed to determine appropriate recovery operations.
F In the event of a severe accident, such as a loss-of-coolant accident, or any other ovent which could lead to significant cladding failures, the levels of radioactivity in the coolant could be high.
Such a situation would require effective control of any resultant leakage.
f*
Our present review procedures does not require dose calculations for passive failures, such as pump seal failures, if charcoal adsorbers are provided for the secondary containment atmosphere exhaust.
Furthermore, the procedure does not require a systematic review by I"
I appropriate secondary review branches to assure that the highly-radioactive post-LOCA water leakage will be handled properly durinq all phases of the post-accident recovery operation.
A systematic review should include review of emergency operating procedures and P'
I technical specifications that are necessary to assure the capability to control leakaqo in a manner that will meet both the first objective (assurino performance of the cooling functions) and the second objective a
(preventing excessive offsite doses).
Because of the inaccessibility P
of the equipment under post-LOCA conditions and the manual operations involved in aligning equipment for loop functions and isolating excessively leakin4 components, advanced planning of the steps involved in controlling the probable leakages for the required long-P' term loop configurations should be set out in emergency operating procedures.
Technical seccifications governing loop boundary integrity, leak detection equipment, isolation equipment and leakage control equipment should be established, including limiting conditions for f*
operation and surveillance requirements.
f ft
O SUE B-6 9 -Icentinusd) dd While cxisting aquipmInt end pract,durcs msy parmit a sucesssful post-accident recovery operation, the current standard review plan does not provide an explicit basis for confirming that these objectives will be met.
IN SCHEDULE: Hono CURRENT STATUS: This task is superseded by TMI Lessons Learned item 2.1.6
" Post Accident Control of Radiation in Systems Outside Containment of PWRs and BWRs" which has been implemented on all plants.
(See HUREG-Id 0578, par 2.1.6).
PROBLEMS:
SUR #
TYPE FLAG STATUS _
PRIORITY TASK A.P.
IECH, RES IMP LEMEN T A TI ON TACS #
UPDATED _
2 B-70 S
RESOLVED HO COMPLETE NOT STARTED 01/00/81 HRR R.
Fitzpatrick (492-8350) PSB/DSI TITLE:
Power Grid Frequency Degradation and Effect on Primary Coolant Pumps GD DESCRIPTION: Offsite power system frequency decay, depending on the rate of decay, could provide an electrical brake on the reactor coolant pump motors that could slow the pumps faster than the assumed flywheel coastdown flow rates normally used in analyzing loss of-flow accidents.
4D Task A-35 will determine a maximum credible frequency decay rate to be used in this task.
This task will determine if any additional measures are necessary to protect against a frequency decay event.
SCHEDULE: HONE 4D CURRENT STATUS: Current staff position on this task is that it is not a significant safety issue in a practical technical sense and should be deleted as a generic safety concern.
Branch Technical position ICSB-15 in Appendix 8A of the SRP which addresses this issue is being deleted.
4D PROBLcMS:
e D
9t 6
e' 9'
o O
f*
)
a f_1 TYPE
_ FLAG STATUS _
ERJ_0RITY TASK A.P.
TECH 2_RES.
IMELEMENIATION TACS 4 UPDATED _
I
.-71
,S RESOLVED HO COMPLETE COMPLEIE Ch TITLE:
Incident Response DESCRIPTION: Present NRC actions taken in response to a serious incident are directed from an Incident Response Center (IRC).
To implement f>
an adequate response, it is necessary that the IRC be equipped with appropriate communications services, information handling and evaluation aids, pre-approved action guidelines, and techncial and management
~
perronnel resources.
The present IRC, which is manned during the P
course of an incident by a team of HRC management and technical staff, has all of thse to some degree.
A joint HRR/IE paper dated July 23, 1976, iddresses whether practical and useful short-term and long-term improvements can be made.
The paper (1) discusses the practicality and need for various IRC resources as a function of the goals of the HRC response capability and the time sequences of a spectrum of incident scenarios judged typical of those that are at least theoretically possible, and (2) makes recommendations with regard to NRR and IE actions to improve the IRC.
The paper was reviewed and discussed by the Directors of HRR and IE, and the implementation recommendations agreed to in principle and a i
i commitment of manpower was made by each of the Directors.
IE F
has had and now has work proceeding in the areas for which they are responsible.
HMSS also has responsibility for contributing to the incident management effort.
SCHEDULE: Hone F
CURRENT STATUS: This issue has been resolved by implementation of past TMI requirements for response to incidents.
PROBLEMS:
i 9
1 i
q.
i
'I 9
f r
f h
__ j
W 5_ME_!
LYf_g FLAG STATUS _
PRIORITY JMK A. P.
IFJH. RE1 JRP_(fMJHLA TION TACS a MPDATEp_.
B-72 L
RESOLVED H0 COMPLETE IH PROGRESS 02/00/81 HRR F. Congol (492-7452)
RAB/DE ap TITLE:
Dsvalopmunt of Medsis for Asssssing Risk of Hralth Effects and Life Shortening from Uranium and Coal Fuel Cycles DESCRIPTION: Current practice in health impact assessments is to convert radiation exposure estimates into estimates of health effects, such er as cancer deaths, illness, and life shortening.
However, the models presently being used, such as those in WASH-1400, GESMO, current NRC case realted testimony, and EPA assessments, all suffer from similar weaknesses.
A major common weakness, which appears amendable to er solution, is realted to the correct treatment of competing risks among populations with life expectancies, age, and sex distributions that vary with time.
Since the staff is currently attempting to assess health effects in the future (e.g.,
Year 2000 and beyond),
er it is reasonable to expect significant changes in current population statistics.
To make such an assessment, a demographic model is required which extrapolates the current population into the future, correctly allowino for competing risks of mortality from various em causes (e.g.,
accidents, heart disease, and cancer).
Failure to do 50 results, for example, in hypothetical cancer deaths for people who would statistically die from other causes.
In the absence of better predictive models, it is not possible to even en evaluate the uncartainty associated with the use of the current simplified methods for estimating health effects and consequent life shortening.
Uncertainties in the use of current models are greatly magnified when attempting to make comparisions of health en effects for the coal and nuclear fuel cycles.
Current health effects models generally are used for estimatino long-term impacts.
Chronic exposure may be the primary determinant er of the number of deaths for a given period for a given pollutant.
However, in the case of non-radiological pollutants from the coal fuel cycle, short-term fluctuations leading to acute exposures may determine the time of death and consequent life shortening.
em Current evaluations of the coal fuel cycle generally fail to account for short-term mortaility, disease and illness.
In addition, short-term effects from chemical pollutants are generally dependent on the prior history of chronic (long-term) er exposure.
Current models generally assume linear dose response relationships even when evidence exists for real or practical thresholds, or g>
where experimental data support a non-linear dose response relationship.
This task involves the development of models to address these problems so that health effects (morbidity and mortality) can be gp assessed for both the coal and uranium fuel cycles as completely as current data permit and on a comparable basis.
SCHEDULE: Update of Draft NUREG-0332 due to be completed in June 1981.
g CURRENT STATUS: Information contained in Draft HUREG is being used 49 j
in Draft and Final environmental statements regarding comparisons i
of coal and nuclear impacts.
j PROBLEMS:
O f
(3 i
(D)
J U( 3
- IJPJ FLAG
_STATU1_
PRIORITY TASK A.P.
TECH. REit IMPLEMENTATION TACS 8 UPDATED B - XJ S
ACTIVE NO INC0t1PLETE HOT STARTED 01/00/81 HRR Shou-Hien Hou (492-9474) MEB/DE P
TITLE: Monitoring for Excessive Vibration Inside the Reactor Pressure Vessel DESCRIPTION: This task involves assessing the need for and, if necessary, developing criteria for acceptable virbration monitoring systems to provide carry warning of excessive vibration inside the reactor vessel.
E' SCHEDULE: Not scheduled CURRENT STATUS: Standard ANSI /ASME OM-5, draft 3 was completed 2/15/80.
MEB has reviewed the draft and concluded that it is aenerally informative and needs refinement in several areas.
Details of P'
MEB comments were delineated in memo of 4/28/80 J. P. Knight to E.
L. Jordan.
PROBLEMS:
i f
e 8'
{
t f
f f
F' f
f 9
f f
f a
f%
iMf_#
TYPE FLAG
_11ATUS PRIORITY TASK A.P.
IECH. RW IMM RTENTATIOJ TACS #
UPDAlfD_
C-1
." S ACTIVE COMPLETE IN PROGRESS 01/00/81 NRR P.
D. Bsnnsdatto (492-8561)
EQB/DE
- 4 TITLE:
Assurence of Continuous Long Term Capability of Hermetic Seals on Instrumentation and Electrical Equipment.
DESCRIPTION: Certain classes of instrumentation incorporate seals.
When safety related components within containment must function during post-LOCA accidentconditions, their operability is sensitive
?
to the ingress of steam or water.
If the seals should become defective as a result of personnel errors in the maintenance of such equipment, such errors could lead to the loss of effective seals and the resultant loss of equipment operability.
The establishment of a basis for ED c on fi den ce that sensitive equipment has a seal during the lifetime of the plant is needed.
If current equipment and practices are found to be inadequate, critoria involving a testable design and/or quality assurance procedures adequate to assure continued seal db integrity may be required.
SCHEDULE: Unknown CURRENT STATUS: This task is part of the environmental 4D qualification of electical equipment which is covered by commission memorandum and order (CLI-80-21).
This work is correcity undreway in the EQB of DE.
This task will longer be carried as a generic task.
no PROBLEMS:
GP EUE #
11P1 FLAG
_ STATUS _
PRIORITY TASK A.P.
IECH. RES.
IMPLEMENTATIQM _TACS #
MPDATED_
4D C-2 L
INACTIVE HQ 1HCOMPLE16 HDT STARIED 04/00/81 HRR J. Kudrick (492-9415) CSB/DSI TITLE:
Study of Containment Depressurization by Inadvertent Spray Operation.
DESCRIPTION: Inadvertent operation of containment sprays can result 4D in a rapid depressurization of the containment building. Who: e containment external design pressure may be exceeded many plants have been provided with vacuum breakers or control system interlocks tb i
to prevent the containment external design pressure from being exceeded.
The depressurization of the containment is a transient behavior and can l
take place in a short time period.
This task involves the developement i
of a code to be used for the analysis of containment pressure response (both with and without the effects of vacuum breakers or control systems)
Eb for the inadvertent spray accident.
SCHEDULE: Expected to be completed in FY-83.
CURRENT STATUS: There has been no work on this activity Gb because of low priority.
PROBLEMS:
I
{
s' I I
\\
r l
F i
i LE_#
TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RES, JMPL[dgNIATIDH TACS 8 UPDATED
'(
N3
- USI ACTIVE YES INCOMPLETE NOT STARTED 05/00/81 TITLE:
Insulation Usaae with in Containment P
DESCRIPTIDH: Various kinds of insulation are being used on.-iping and components inside the containment of a nuclear power plant.
Of concern is its behavior under pipe break accident conditions with j
a regard to the potential for blocking vent paths in subcompartments and F
q impairing the effectiveness of the containment emergency sumps.
The purpose of this task will be to ga!n a better understanding of how insulation night behave under pipe break accident conditions. This information will then be used to assess the assumptions made regarding P
insulation behavior for subcompartment analysis and the need for revising containment emergency sump desigo requirements.
1 SCHEDULE: See AQUA Book, HURE 0606.
4 CURRENT STATUS: This task is included in USI A-43, " containment d'
emergency service performance".
PROBLEMS:
9 UL_4 IYPg FLAG STATUS PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATIDH TACS #
UPDATED
- -4 L
TITLE:
Statistical Motheds for ECCS Analysis DESCRIPTION: Appendix K 10 CFR 50 specifies the requirements for LWR 8"
ECCS analysis.
These requirements presently call for specified conservatisms to be applied to certain mo-els and correlations used in the analysis to account for data uncertainties at the time Appendix K was wrtten.
The resulting conservatism in the calculated f*
peak clad temperature however, has never been compared against the uncertainty in peak clad temperature obtained from a realistically calculated (best estimate) LOCA.
i In order to assess the safety margin in the Appendix K requirements, the peak clad temperature requirement (2200 degree F) will be equated to an uncertainty level of a realistic calculation.
This will be accomplished by analytical analysis utilizing best estimate LOCA analysis F
codes in which certain input parameters are simultaneously varied about their uncertainty distribution functions such that a resulting uncertainly distribution functions in peak clad temperature is obtained.
It is then possible to express the conservatism of the 2200 degree F cladding temperature F
limit in terms of probability and/or standard deviations from the most probable peak clad temperatur.
The statistical methods for ECCS analysis will provide a probabilistic quantification of the safety margin imposed by 10 CFR 50 Appendix K ECCS safety evaluation requirements.
The results d'
of this program will be used to aid the staff in the review of changes to vendor ECCS models and in performing staff audit calculations of ECCS performance.
SCHEDULE: Not established.
F CURRENT STATUS: Unknown - This task is not an identified safety concern.
PROBLEMS:
P 9
l l
p l
f>
{
4 SUE #
11P_E FLAG
_S T A T UL PRIORITY TASK A.P.
LECH. RF1 JJJP M E M M LDE TACS #
[lP_DMJH_
C-5 L
RESOLVED H0 COMPLETE NOT STARIED 04/00/81 HRR Dzn Fieno (492-7579) CPB/DSI gb TITLE:
Decay llcat Update DESCRIPTION: This task involves following the work of rescarch groups in determinino best estimate decay heat data and associated uncertainties for use in LOCA calculations.
The results of this 4b task could be incorporated in future revisions of the current regulations regarding ECCS performance.
SCHEDULE: Not established.
CURREtiT STATUS: HRC has followed the development of AHS standard 5.1 9
prooosed guidelines.
AHS 5.1 applies to Appendix K type calculations.
The staff does not interst to propose rulemaking to enarge 10 CFR 50, Appendix K.
This issue is considered to be resolved.
PROBLEMS:
9 5UE #
TYPE FLAG
_STATU1_
PRIORITY TASK A.P.
IECH. R ES.
IMPLEMENTATION TACS #
UPDATED _
C-6 L
RESOLVED HO C0t1PLETE 04/00/81 9
HRR Dan Fieno (492-7579)
CPB/DSI TITLE:
LOCA Heat Sources DESCRIPTION: The contributers to LOCA heat sources, along with their associated uncertainties, and the manner in which they are combined 9-have an impact on LOCA calculations.
An evalution of the combined effect of power density, decay heat, stored energy, fission power decay and their associated uncertainties with regard to calculations of LOCA heat sources is needed.
This task will involve the review of GI.
vendor's data and approaches for determining LOCA heat sources and developing staf f posi tions as needed.
SCHEDULE: Not established.
CURRENT STATUS: This issue was intended to be an open item to cover GP work to improve predictions of heat sources for LOCA calculations.
It is not an identified safety issue.
It is cosidered to be resolved.
PROBLEMS:
W 4
e DT O
D 4
f EUE_e o ',1YP_E FLAG
_SIAIUS_,,
PRIORITY TASK A.P.
LECH. REi,,
HPQA_lER_
C-7 5
RESOLVED H0 COMPLETE HOT STARTED 01/00/81 NRR S. Pawlicki (492-7687) 8" TITLE:
PWR System Piping DESCRIPTION: Combinations of fabrication, stress and environmental have resulted instances of stress corrosion cracking of low pressure schedule 10 type 304 stainless steel piping systems.
Although these systems F
are not part of the reactor coolant pressure boundary, they are safety related; e.g.,
the containment spray system.
The incidence of cracking.
has been restricted to thin wall, low pressure, low flow systems.
These cracks have occurred adjacent to the weld zones of the thin-walled piping P
after approximately three to five years of service and were identified by volumetric examination, by leak detection systems, or by visual inspection.
In each of the cracking events that have occurred to date, the affected piping was determinnd to have been sensitized and, therefore, particularly vulnerable I
to corrosive attack.
Current licensi-~ criteria preclude the use of sensitized piping in safety-related piping 7vstems and place increased emphasis on the use of corrosion-F resistant material in such systems.
The purpose of this task is to continue to evaluate operating experience to determine if augmented inservice inspection requirements should be established to further enhance the reliability of such piping systems.
P SCHEDULE: Hot Developed.
CURRENT STATUS: Resolution is published in NUREG-0691 DST has been requested to evaluate recommendation for implementation contained in HUREG.
P PROBLEMS:
fUE #
TYPE FLAG
_,,$ T A T U S_
PRIORITY TASK A.P.
_1EC!!mREL J1]PQt1ENT ATION TACS 8 UEpA LED _
f' C-8 5
INACIIVE HD INCOMPLETE NOT STARTED 04/00/81 HRR Ted Sullivan (492-7025)
TITLE: Main Steam Line Leakage Control Systems DESCRIPTION: Operational experience has indicated that there is a relatively high failure rate and variety of failure modes for components of the main steam isolation valve leakage control systems (MSIV-LCS) in certain operating BWRs.
Experience from surveillance testing and reported in recent LERs is being compiled by DDR to serve as a basis for identifying design improvements I
and preparing recommendations to DSS and DSE for consideration in terms of future revisions to Regulatory Guide 1.96, changes to the Standard Review Plan, and implementation on pending licensing cases.
SCHEDULE: Not Scheduln.
P CURRENT STATUS: There has been no activety on this task for several years.
Status of previous work is unknown.
in HUREG.
PRO B L Ef15 :
F F
f-9 f
O LUE # * ]D21 FLAG STATUS _
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS #
UPDATED
[C-9 5
HRR Hot assignid.
Eh TITLE:
RHR Heat Exchanger Tube Failures DESCRIPTIDH: RlW beat exchangers are designed to bring the reactor to a safe cold shutdown condition and to maintain the core in a coolable geometry following a postulated loss-of-coolant accident.
In the recent past, there
$d have been several RHR heat exchanger tube failures at DWRs.
Since the pressure control system on the river water (shellside) piping system maintains the pressure of the river water in the shellside of the RHR heat exchanger greater than the primary coolant pressure in the tubeside of the RHR Od exchanger during plant cooldown operations, a leak in the tubes would result in back leakage of river water into the primary loop.
The objective of maintaining the pressure in the shell side greater than that in the tubeside is that in the event of a tube failure there would be no leakage of redioactive GP fluids into the environment.
This task will investigate the cause of these tube failures and the design of the pressure control system to assure that adequate long term core cooling capability is available.
SCHEDULE: Unknown GD CURRENT STATUS: Unknown PROBLEMS:
>UE a YPE FLAG
_iIaltEt ERIORITY le_SK A.P.
TECH. RES.
IUP_LEdgNI A_TI2i TACS #
UPDATED C-10 L
IHACTIVE NO INCOMPLETE NOT STARIED NRR T. Quay (492-7860)
AEB/DE TITLE:
Effective Operation of Containment Sprays in a LOCA db DESCRIPTION: This task will respond to a conern of the ACRS about the effectiveness of various containment sprays to remove airborno radioactive materials which could be present within the containment follcwing a LOCA.
This concern has been expanded to include the possible damage to equipment 45 located inside containment due to an inadvertent actuation of the sprays.
This task involves assisting the industry in writing an ANSI Standard on the design of containment spray systems, developing a topical report on the 4D techiological baser for spray washout models, and in managing contract to evaluate the ability of different spray solutions to remove the radioiodines and radioactive particulates released to containment during a postulated LOCA.
S Draft 7 of ANSI HS81, "BWR and PWR Containment Spray System Design", has been reviewed by the staff.
Following resolution of the NRC comments and issuance of this standard by ANSI, a regulatory guide endorsing this standard will be developed.
GP SCHEDULE: Hot Scheduled CURRENT STATUS: Task largely completed although not completely documented.
Needs re-evaluation to determine if additional work needs to be done.
PROBLEMS:
G>
S 9
O
f I
SUE.s..TlP_f FLAG
_ STATUS PRIORITY TASK A.P.
IECH. REL JMPLEMJHIA T I_0_tf TACS :
U P_D_Alf D_
C-11
- USl AC11VE YES INCOMPLETE NOT STARTED 05/00/81 HRR Andy Marchese (492-8230)
GIB/ DST 8"
TITLE:
Assessment of Failure and Reliability of Pumps and Valves.
DESCRIPTION: The operating experience of nuclear power plants indicates that a number of valves, valve operators and pumps fail to operate as specified in the technical specifications either under testino conditions or when they 8"
are called upon to perform.
The operating experience is documented by the Office of Management Information and Program Control (MIPC) publications in a monthly repor t of LERs sorted by components which include pumps, valves, and valve operators. Most of these occurrences relate to valve leakage, valve act-8P uation, and safety / relief valve operation outside their operational bounds.
The main steam isolation. safety and solenoid valves caused the most frequent abnormal occurrences in safety-related systems.
Valve malfunctions can cause forced outage of operating plants.
It is noted that about 10% of all outage 8*
time can be attributed to the malfunction of the critical pumps and valves within the plant.
Of primary interest are outages caused by the main stean isolation and safety / relief valves.
9 Several adverse operating experiences concerning main steam isolation valves (MSIVs) were reported to the Office of Inspection and Enforcement following operational tests and spurious closures at various PWR plants.
This led to a staff investigation of MSIVs at all operating and near operating facilities.
f*
This investigation has recently been completed.
The principal activity under this task will be the esaluation of active pump and valves with respect to their operability and reliability under accident loading, 8'
i.e., loss of coolant accident and safe shutdown errthquake.
SCHEDULE: Hot Scheduled CURRENT STATUS: THis task is included in the scope of USI A-45, " Shutdown Decay heat removal Requirement" See AQUA book for status.
8" PROBLEMS:
f>
f>
P P
f*
b r
8
eUE 8 TYPE FLAG STATUS PRIORITY TASK A.P.
TECH. RE12 IUP(fMENIATION TACS #
UPDATED C-12. L YES INC0f1P L E T E NOT STARIED o
HRR Nat assioned
$3 TITLE:
Primary System Vibration Asssssm:nt DESCRIPTION: Structural damage to the primary system, including the reacter pressure vessel and internals, associated piping and steam generator tubing in PWR's, can be caused by vibrations of sufficient magnitude.
These vibrationss II can be either flow-induced or the result of operation of the pumps to which primary system piping is attached.
There have been a number of instances where components internal to the ractor coolant pressure boundary have come loose as the result of flow-induced vibration and been carried through the pri-IN mary system by the coolant flow.
Excessive core barrel movement, caused by flow-induced vibration, may lead to many detrimental effects including damage to reactor internals and interference OS with control rod movement.
Problems resulting from excessive core barrel movement have been encountered at Palisades and possibly other operating plants.
Structural damage due to flow-induced vibration of steam generator tubing has Sh also been encoutered.
Anti vibration bars are currently utilized to minimize tube vibration.
However, fretting has occurred due to deficient design and material selection for the anti vibration bars.
9 Piping systems are also susceptible to forced vibration as a result of pump vibration during operation.
If a natural frequency of the connected piping is very nearly the same as the driving frequency of the pump there is then the possibility, depending on the amplitued of vibration, for fatigue failures in Ub the system, particularly at the nozzle where the stresses will be highest.
Preoperational testing of reactor internals, piping systems and mechanical equipment conducted during startup functional testing to assure structural GD and functional integrity per section 3.9.2 of the Standard Review Plant and Regulatory Guide i.20.
However, vibration frequency shifts are possibic during operation as a result of component and/or component support wear or degradation.
Also, vibration effects for the long term may not have been pro-O perly assessed during startup testing.
Inservice inspection during the life of the plant and possible visual and audible deiection of vibreation during plant operation may be necessary in GD order to arrest structural damage s1 ready incurred or, if the vibration were to continue, might occur at some future time.
This vibration assessment could lead to modifications in the design of system components or component support arrangements.of system operation sequences.
GP SCHEDULE: Not Scheduled CURRENT STATUSt Unknown PROBLEMS:
O 9
l f
1 6'
GP l
i s
r-l 1E_8 O' TYPE FLAG
_ STATUS _
PRIORITY TASK A.P.
IECH. RES.
IMPLEMENTATION TACS 8 MP_DATEQ_
C,13'
'USI ACTIVE YES IllCOMPLET E 05/00/88 8"
NRR Frank Coffman (492-8058)
SIB /DSI TITLE:
Nan Random Failures DESCRIPTION: This is an ACRS generic concern.
It formerly was referred to as common mode failure of identical components exposed to identical or nearly i
P identical conditions or environments.
The concern now has been expandnd to include other typns of multiple failures for which the consequences and probabilities cannot be predicted by application of the single failure criterion, such as use of the same sensors or components for both control f
8" I
and protection system, sequential multiple failures due to a domino effect, or simultaneous multiple failures dueto a single fault. This task has been
{
included in Tasks A-9, A-30, A-35. B-56, and B-57.
)
SCHEDULE: See USI A-17 F
CURRENT STATUS: This task is included as part of USI A-17, " system interaction".
I PROBLEMS:
9 9
P 0
i
\\
f P
t P
j
'I
[
P P
l f
gm I
I PN
L#
TYPE FLAG
,_STATQS_
PRIOPITY TASK A.P.
TECH. RES.
JfP.L EMEN T A TION VASS #
UP_DAlgD P
C-14 L
INACTIVE 01/00/81 NRR W.
Fliegel (492-8003)
HGEB/DE 4D TITLE:
Storm Surge Modes for Coastal Sites
'l DESCRIPTIDH: The primary tool used by the staff for estimating storm surge has been the bathystrophic model developed by the US Army Corps and Engineers.
Coastal, Engineering Research Centeru The model has served its intended 4D purpose will, but bigaer, faster coiputers can handle multidimensional, multivariability models.
These models can be'used in a less conservative I
mode to account for irraqular shoreline and shape facters ignored by the bathystrophic.
This issue is not an identified safety problem.
- However, 4D more complex modelt would allow single step solution of coastal flooding problems.
SCHEDULE: No Schedule CURRENT STATUS: Currently the technical community is developing and attempting 4>
to verify more complex model. However, limitation of data defining both the storm and surge in time and space impede validation.
The HRC is cosponsoring data aquisition proposed and is cooporating in model assessment.
This task provides the forum for NRR staf f activities in this area.
This task provides for 4D continous tracking and assessment of model evalution and data acquisition pro-grams.
PROBLEMS:
O SUE #
TYPE FLAG STATUS _
PRIORITY TASK A.P.
IRCB _RES.
JUP LEMENT ATIQB TACS #
RPDATED_
C-15 L
INACTIVE YES IHC0f1P L ET E HOT STARIED 01/00/81 HRR R.
Bangart (492-7633)
ETSB/DSI (D
TITLE:
HUREG Report for Liquids Tank Failure Analysis DESCRIPTIDH: Standard Review Plan 15.7.3 requires an analysis of the consequences of failure of tanks containing radioactive liquids outside containment.
This task involves the development of a NUREG report that will describe a consistent GD and acceptable method for analyzing the effects of a failure of a radioactive liquid waste tank.
SCHEDULE: Not Scheduled CURRENT STATUS: No action has started on this items due tu low priority and lack 4D of manpower.
PROBLEMS:
S Ek F
en I 7
i O
65
f HUE 8 o ' TYPE FLAG STATUS _
PRIORITY TASK A.P.
TECH. RES.
IMPLEMENTATION TACS 4 QPDATED_
l C-M-E ACTIVE HD IHCOMPLETE 01/00/81 HRR G. Gears (492-4807)
EEB/DSE f*
i TITLE:
Assessment of Agricultural Land in Relation to Power Plant Siting and Cooling System Selection DESCRIPTION: Interpretations of HEPA require that environmental impact assessment include land use impacts and alternatives in nuclear power plant licensing cases.
8' The staff has performed both economic and non economic land resource assessments in compliance with these HEPA requirements.
Recent licensing cases have questioned the adequacy of the staff's resource evaluative methods with respect to large land areas required for sites and cooling lakes.
The primary issue concerning the staff's 8'
assessment is that neither economic analyses nor resource assessment as currently performed provides a convincing rationale for preemption of high quality land in view of continued population pressures, predicted impendinq lags in world-wide agricultural food production and probable increasing international demands on the United States for f'
exports of agricultural products.
Food and fiber production and distribution rank with energy production and utilization as vital world problems now and for the forsceable future.
These problems are inextri-8" cably linked sinco energy production facilities can be consumnrs of large land areas while energy is a prime requirement for even modest levels of agricultural production.
Thus, land use is and prooab'y will remain a key siting issue in nuclear plant licensing.
WP This task will involve the conduct of a confirmatory exploration of net energy techniques to determine their suitability for application to environmental licensing assessment under HEPA.
A problem of immediate licensing consern is the conflict in land use which occurs when power plants with large cooling lakes are sited in regions of prime 8'
agricultural land.
SCHEDULE: Hot Scheduled CURRENT STATUS: ESRPs and Regulatary guide 4.2 will be revised upon completion of review of contracter work.
This action awaits submittal of contracters work f"
(due Spring 1981) and is also depending on availability of staff.
PROBLEMS:
d>
5VR #
TYPE FLAG
_3TATUS_
PRIORITY TASK A.P.
IECH. RES.
? IMPLEMENTATION TACS #
MPDAIEQ_
C-17 L
IHACTIVE HD INCOMPLETE 01/00/81 Richard Bongant (492-7633)
ETSB/DSI TITLE:
Interuir Acceptance Aiteria for Solidification Agents ror 8*
Radioactive Solide Wastes DESCRIPTIDH: There are no current criteria for acceptability of solidification agents.
This task involves the development of criteria for acceptability of radwaste solidification agents to properly implement a process control program f"
for the packaging of diverse plant waste for shallow land burial.
SCHEDULE: Not Schedule CURRENT STATUS: Ho active is underway.
Hocessary prerequirements is acceptance criteria for solidified waste for shallow land burial sites being developed 8"
by HMSS.
All manpower expenditives have been stopped except for coordination with NMSS concerning their criteria developm:7t.
PROBLEMS:
t*
f*
r f
1_UE_8 TYPE FLAG
_3TATUS_
PRIO7ITY TASK A.P.
IECH. RES.
IMPLEMENTATION TACS #
UPDATEQ_
D-1 S
INACTIVE HD INC0f1PLETE 01/00/81 9'
HRR Not Assignsd
()
TITLE:
Advissbility of a Soismic Scram DESCRIPTION: The ACRS has recommended that studies be made of techniques for seismic scram and of the potential safety advantages and potential disadvantages of prompt reactor scram in the event of strong seismic motion, say more than lI one-half the safe shutdown earthquake.
Various suitable techniques have been identified and exist, but thus far only limited studies have been reported on the pros and cons of seismic scram.
SCHEDULE: Not Schedule lh CURRENT STATUS: No activity on this issue.
ACRS still considers this to be of concern.
PROBLEMS:
kUE_8 TYPE FLAG
_ STATUS _
PRIORITY TASK A.P.
IfCH, RES.
IMPLEMEEIATION TACS #
UPDATEQ_
FD-2 L
INACTIVE NO INCOMPLETE NOT STARTED 01/00/81 i
NRR Not Assigned TITLE:
Emergency Care Cooling System Capability for Future Plants II DESCRIPTION: This is an ACRS generic concern.
It involves exploratinn of diverse means of obtaining ECCS capability.
SCHEDULE: Not Schedule CURRENT STATUS: Unknown PROBLEMS:
- UE s TYPE FLAG STATUS _
PRIORITY TASK A.P.
TECH. RES.
IMPLfdgy1AllpH TACS 4 UPDATED lI D-3 S
RESOLVED NO Cat 1PLETE NOT STARIED HRR Dan Fieno TITLE:
DESCRIPTIDH: This is an ACRS generic concern.
It involves assessing tSe uncertainties lI in calculations of the control drop accident including the choice of negative reactivity insertion rate due to a scram and the pote:Alal differences between a two-dimensional and a three-dimensional calculation.
SCHEDULE: Complete II CURRENT STATUS: Completed and closed out by later to E. J. Case from R. J. Mattson dated March 6, 1978
Subject:
Task No. D-3 central Rod Drop Accident.
PROBLEMS:
1 lI lI 1
$h :
l
$p l>
lD l 0
l l
kh GD I 1