ML20063M410
| ML20063M410 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/27/1980 |
| From: | Grier B, Snyder B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), Office of Nuclear Reactor Regulation |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20063M411 | List: |
| References | |
| IEB-79-05, IEB-79-5, NUDOCS 8209140052 | |
| Download: ML20063M410 (19) | |
Text
- -
4
[@* "8 Cog UNITED STATES
! Yg>y.([h' p, NUCLEAR REGULATORY COMMISstON wAss:NcTou, o, c. 20sss 5
5
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l 1
]
Docket No. 50-289 i
MENORANDUM FOR:
Branch Chiefs /Section Chiefs, Region I i
TMI Program Office FROM:
B. H. Grier, Director, Region I B. J. Snyder, Program Director, TMI Program Office i
SUBJECT:
THREE MILE ISLAND, UNIT 1, RESTART INSPECTION PROGRAM
REFERENCES:
(a) GPUSC letter to NRC/NRR, dated June 27, 1979; Modifications / Actions to be Completed Prior to the TMI-1 Restart (b) USNRC Order and Notice of Hearing in the ;!atter of Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit No.1), dated August 9, 1979 (c) HUREG-0578, TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations
]
(d)
IE Bulletins79-05A, 79-05B, and 79-05C i
(e) Director, Region I, memorandum, dated January 28, 1980; same subject i
1.
This memorandum directs the implementation of a special inspection program, structured to provide an intensive review of the Three Mile Island Unit 1 restart activities, based upon commitments and requirements contained in references (a) through (d).
The program includes both normal MC 2515 inspection requirements to be completed on an expeditious basis and supplemental inspection requirements relative to the many and various restart activities.
Reference (e) is superseded in.its entirety by this memorandum.
- 2. lists specific MC 2515 inspection procedures required to be completed prior to TMI-l restart.
Section assignments for performing each inspection procedure (IP) are listed below each IP l
number using the following abbreviations.
8209140052 800527 PDR ADOCK 05000289 G
PD(
Q
. -,.. -, -,, ~ -
Multiple Addressee 2
ESl - Engineering Support Section No. 1, RC&ES Branch ES2 - Engineering Support Section No. 2, RC&ES Branch E&SP - Environmental and Special Projects Section, FF&MS Branch NSl - Nuclear Support Section No.1, RO&NS Branch NS2 - Nuclear Support Section No. 2, RO&iiS Branch RS - Radiation Support Section, FF&MS Branch S&I - Security and Investigation Section, Safeguards Branch TMI - TMI Site Operations Section, TMI Site Staff Normal MC 2515 inspection frequencies are listed for each IP, as well as inspection windows for starting and completing each IP, based on months prior to Restart (R) or 100% Power Operation (P).
- 3. lists specific MC 2513 and MC 2514 inspection procedures which are applicable to the "preoperational" and "startup testing" aspects of the TMI-l Restart activities. Each IP number, which ends with an "R" to identify the inspection effort as associated with TMI-l Restart, corresponds with a "B" inspection procedure of the MC 2513 and MC 2514 programs. Section assignments for performing each inspection procedure and inspection windows are listed as described above.
- 4. lists specific modifications requiring NRC approval, which are required by NRC Order or licensee commitment to be completed prior to or after TMI-l Restart.
Each of these modifications requires inspection per IP 377018 and in most cases per IP 727018.
Known requirements for performing IP 55700B, 57700B, and 63700B are also listed, recognizing that additional requirements for performing these inspection procedures may be identified when completing 37701B.
S.
Fnclosure 4 lists specific requirements of reference (b), which are categorized into variou.c inspection areas.
The enclosure is provided as an inspection aid so that requirements similar in nature are reviewed for compliance during anticipated special programmatic inspections.
Multiple Addressee 3
6.
Each Region I Section Chief should review the enclosures to identify those inspection procedures assigned for completion.
A schedule for performing assigned IPs should be submitted to R. Keimig as soon as possible, but no later than May 30, 1980.
For inspection scheduling purposes, assume a THI-l Restart (R) of March 31, 1981, and 100% Power Operation (P) of May 31, 1981.
Identify the period (s) for completing each inspection procedure (and the inspector designated to perform each IP if known).
Inspection procedures which require assistance from outside Regicn I to complete should be identified to the Director, Region I.
7.
An integrated inspection schedule for TMI-l Restart will be prepared by D. Haverkamp by June 15, 1980, based upon inputs provided to R. Keimig, above. The integrated inspection schedule will also-indicate responsibility for reviewing IE Bulletins and other matters in response to IE Manual temporary instructions.
B. H. Gri' Director Region I
/
gd _
B. J. Sn der Program irector TMI Program Office
Enclosures:
As stated cc:
V. Stello H. Denton J. Collins A. Fasano M. Shanbaky D. Haverkamp R. Keimig
INSPECTION PROCEDURES - TMI-l 0PERATIONS PHASE Procedure fiumber May be Must be Must be (Assionment)
Title Started Started Complete 3u703B l
Mu-agement Meeting - Entrance and (ALL)
Exit Interviews (Each Insp)'
Each Ins pection--
3S7016 l (hS'i)
QA Program - Annual Review (A)
R-9 R-6 R-3 35751B (NS2)
QA/QC Administration Program (3yr)
R-9 R-6 R-3 36700b Organization and
_(dS2)
Administration (A)
R-9 R-6 R-3 367018 Qualification of Personnel (NS2)
Program (3 yr)
R-9 R-6 R-3 37700B Design Changes and (NS2)
Modifications (A)
R-9
_ -6 R-3 R
37701B I
I I
(ESl/ES2)
Facility Modifications (W)
R-9 R-6 R-3 377028 Design Changes and liodification (NS2)
Program (3yr)
R-9 R-6 R-3 37703B Tests and Experiments (NS2)
Program (3yr)
R-9 R-6 R-3 38701B Procurement Control (NS2)
Program (3 yr)
R-9 R-6 R-3 387028 Receipt, Storage and Handling of (NS2)
Equipment Program
-(3 yr)
R-9 R-6 R-3 39701B (NS2)
Records Program (3 yr)
R-9 R-6 R-3 397028 (NS2)
Document Control Program (3 yr)
R-9 R-6 R 407008 I
Onsite Review Committee (A)
R-9 R-6 R-3
_(gg) 407018 i
(riS2) l Offsite Review Committee (2 yr)
R-9 R-6 R-3 407028 (NS2)
Audit Program (3 yr)
R-9 R-6 R-3~
40703B (iiS2)
Offsite Support Staff (2 yr)
R-9 R-6 R-3
INSPECTION PROCEDURES - TMI-l OPERATIONS PHASL
' Procedure Number May be Must be Must be (Assignment)
Title Started Started, Complete 40704B (NS2)
Implementation, Audit Program (A)
R-9 R-6 R-3 41700B (NS1)
Training (A)
R-6 R-3 R-1 41701B (NSI)
Requalification Training (A)
R-6 R-3 R-1 42/006 (HS2)
Procedures (A)
R-9 R-6 R-3 347018 Housekeeping / Cleanliness (NS2)
Program (3 yr)
R-9 R-6 R-3 55700B I
l I
(ESl)
Welding (W)
R-9 R-6 R-3 56700B (NS2)
Calibration (A)
R-9 R-6 R-3 57700B I
I I
(ESl_)
}
Nondestructive Examination (W)
R-9 R-6 R-3 61700B (NS2)
Surveillance (A)
R-9 R-6 R-3 617018 Surveillance (R)
R-6 R-3 R-1 (NS1)
~~
617248' Test and Measurement Equipment (NS2)
Program
'(3'yr)
R-9 R-6 R-3 61725B Surveil!ance Testing (NS2)
Program (3 yr)
R-9 R-6 R-3 61726R (THI)
Monthly Surveillance Observation
--Monthl y---------
62700B
_(NS2)
Maintenance (A)_
R-9 R-6 R-3 62701B
_(NS2)
Maintenance (R)
R-9 R-6 R-3 b27028 (NS2)
Maintenance Program (3 yr)
R-9 R-6 R-3 62703B Monthly
_(TMij Maintenance Observation
--Monthl y---------
f, I
\\
i 2
INSPECTION PROCEDURES - THI-I OPERATIONS PilASE
- Procedure Humber May be Must be Must be
{As signmen t)
Ti tle Started Started Complete 637006 (ESl/ES2)
Construction Testing (W)
R-9 R-6 R-3 l
I I
64703B Fire Prevention / Protection
-(ES2)
Program (3 yr)
R-9 R-6 R-3 bow (TM1 er
--Monthi v---------
717136 (Thl)
R-9/R-R-7/R-lf Review of Plant Operations (S)
R-6/R 72700B (NS1)
_Startup Testing - Refueling (R)
P-3 P-1 P
72701B Startup Testing - New or Modified (NSI)
System (W)
P-3l l
I P-l P
73051B Inservice Inspection - Review of (ESI)
Program (W)
R-92 R-62 p_32 73052B Inservice Inspection - Review of (ESl)
Procedures (W)
R-9 R-6 R-3 2
2 2
Inservice Inspection - Observation 73753B of Work and Work (ES1)
Activities (R)
As deter nined by E Sl 737550 Inservice Inspection - Data Review (ESl) and Evaluation (R)
As deter lined by E S1 80710B (E&SP)
Environmental Protection (A)
R-6 R-3 R-1 81121B (S&l)
Security Plan (W)
R-9 R-6 R-3 81123B (S&l)
Security Program Audit (A)
R-9 R-6 R-3 81125B (S&f)
Security Organization (S)
R-9/R-3 R-7/R-1 R-6/R 81127B Physical Barriers (S&I)
(Protected Area)
(S)
R-9/R-3 R-7/R-1 R-6/R (S I)
Physical Barriers (Vital Area)
(S) i R-9/R-3 R-7/R-1 R-6/R 81131B (S&l)
Lighting (S)
R-9/ R-3 R-7/R-1 R-6/R 3
If4SPECTION PROCEDURES - TMI-l OPERATIONS PHASE Procedure Humber May be Must be Must be gssignment)
Title Started S ta rted Complete l
811.3B Access Control (Identification, (S&I)
Authorization, & Badging)
(S)
R-9/R-3 R-7/R-1 R-6/R 811358 (S&I)
Access Control (Search)
(S)
R-9/R-3 R-7/R-1 R-6/R 81137B (S&I)
Access Control (Escorting)
(S);
R-9/ R-3 R-7/R-1 R-6/R i
81139B Access Control l
(S&I)
(Vital Areas)
(S)l R-9/R-3 R-7/R-1 R-6/R
)
81141B
~
(S)
R-9/R-3 R-7/R-1 R-6/R (S&I)
Alarm Stations 81143B (S&I)
Detection Aids (S)
R-9/R-3 R-7/R-1 R-6/R 81145B (S&I)
Assessment Aids (S)
R-9/R-3 R-7/R-1 R-6/R 811478 l
(S&I)
Communications (S)
R-9/R-3 R-7/R-1 R-6/R l
811498 Testing and Maintenance (S)
R-9/R-3 R-7/R-1 R-6/R (S&I) 811518 5
(S&l)
Compensatory Measures (S)
R-9/R-3 R-7/R-1 R-6/R 81153B
~~
(S&I)
Power Supply (S)
R-9/R-3 R-7/R-1 R-6/R 81155B (S&I)
Response
(S)
R-9/R-3 R-7/R-1
,R-6/R 81157B (S&I)
Locks, Keys and Combinations (S)
R-9/R-3 R-7/R-1 R-6/R 81159B (S&I)
Records and Reports (S)
R-9/R-3 R-7/R-1 R-6/R tmergency Planning - Agreements 827108
& Coordination with Offsite (E&SP)
Agencies (A)
R-9 R-6 R-3 82711B Emergency Planning - Facilities (E&SP)
& Equipment (A)
R-9 R-6 R-3 827128 Emergency Planning -
(ESSP)
Test & Drills (A)
R-93 R-63 R-33 4
IllSPECTION PROCEDURES - TMI-l OPERATIONS PHASE Procedure Humber May be Must be Must be (Assignment)
Ti tle Started Started Complete 1
i 837408 Radiation Protection -
(RS)
Operation (A)
R-9 R-6 R-3 g
84710B l
Radioactive Waste Systems, (RS)
Operation (A)
R-9 R-6 R-3 Radioactive Waste Systems, QC 847118 and Confirmatory (E&SP)
'ieasurement (A)
R-9 R-6 R-3
~
867188 Periodic Maintenance of
~
(3 yr)
R-9 R-6 R-3 (RS)
Packagings 66740B l
(RS/TMI)
Transportation Activities (A)
R-9 R-6 R-3 90712B Inoffice Review of (TMI)
Event Reports (W)
Upn Receip1 90713B Review of Periodic and To be Determined (THI)
Special Reports (W)
Upon Recei pt--
90714B l
NonroJtine Reporting (TMI) l Program (3 yr)
R-9 R-6 R-3 92700B To be De termined (TMI)
Licensee Event followup (W)
Upon Receipt--
Followup on Inspector-l 92701B Identified Problems To be Determined l
Unresolved Items (W) as Appropriate (ALL)
-Foflowup on Items on 927028 Honcomp1iance/
To be De tennined (ALL)
Deviations (W) as Appropriate, l
92703B IE Bulletin / Circular /Immediate To be De termined l (Ti11)
Action Letter Followup (W) as appropriate 9270SB As Sched.21ed by4 (ALL)
Followup on Regional Requests Regi ]n I------
92706B Independent Inspection As Sched sled by (ALL)
Effort (Each Insp)
Each Inspector 927098 followup on Licensee's To be De tennined (TNI)
Plans for Coping with Strikes as Appropriatt 92710B Followup on Initial Licensee To be De termined (Tlil)
Implementation of Strike Plan as fppropriatt Followup on Continued Licensee 927118 Implementation of Strike Plan Weekly c uring (IMI)
During an Extended Strike Strike __
5
INSPECTION PROCEDURES - THI-l OPERATIONS PHASE Procedure Humber May be Must be Must be
( As signraent)
Ti tle Started Started. C6mplete Followup on Resumption of 92712B Normal Operations After To be Determined (THI)
A Strike as _Appropria Le 92716B (TMI)
Review of Part 21 Reports Upon Receipt 92716B To be Ietermined (TMI)
Part 21 Report Followup Upon Receipt Followup on Significant 93701B Event that Occurs During To be l?etermined (TMI)
Inspection as Appropria te 93702B Plant Trips - Safety To be Determined (TMI)
System Challenges as Appropriate 946006 Information Meetings with To be Determined (TMI)
Local Officials as Appropriate 947008 Participation in To be
)eterminec (ALL)
ACRS Meeting as Appropria te 947018 Recommendations Regarding To be Jeterminec (ALL)
Licensee Modification as Appropria te 947028 Participation in NRR/
To be
)eterminec (ALL)
Licensee Meeting as Appropria te 94703B To be )eterminec (THI)
Media Contacts as, Appropria.te 6
Enclosqre 1
I NOTES:
I Refer to Enclosure 3 for specific listing of modifications requiring inspection per procedures 37701B, 55700B, 57700B, 637008, and 72701B.
2 Inspection procedures 730518 and 730528 are recommended for completion as indicated.
Inspection procedures 73753B and 737558 are to be performed as deemed necessary by the Chief, Engineering Support Section No.1.
3Emergency drill (s) should be witnessed per Inspection Procedure 82712B.
THI Site Staff inspectors should provide support to the coordinating E&SP radiation specialist during the inspection (s).
4Inspection effort in addition to that required by this program,
{
specifically directed by Region I, should be documented under Inspection i
Procedure 32705B.
I l
l l
7 ;:
litSPECTION PROCEDURES - TMI-1 RESTART PHASE Procedure liumber May be Must be Must be
,( As signr.1en t)
Ti tle Started Started Complete 3530lR Quality Assurance for Preoperational (NS2)
Testing R-9 R-6 R-3 3650lR Quality Assurance for Startup 3
(NS2)
.esting Program P-6 P-3 P
~
7030lR Overall Preoperational Test Program (rtS1)
Review Requirements R-9 '
R-6 R-3 70302R Preoperational Test Program (riS1)
Implementation R-6 R-3 R-1 70303R Preoperational Test Procedure (liS1)
Review R-9 R-G R-3 70304R Preoperational Test Procedure *
(NSl)
Review R-9 R-6 R-3 70300R Preoperational Testing Procedure (l151 )
Review - RPS R-9 R-6 R-3 7030bR Preoperational Testing Procedure (NSl)
Review - LOP R-9 R-6 R-3 PreUperational Tesi.ing Procedure 70307R Review - (Containment Leak Rate (NS1)
Testing)
R-9 R-6 R-3 Preoperational Testing Procedure 70308R Review - (Integrated Hot Functional II-9 (NSl)
Testing)
R-6 R-3 70311R Preoperational Testing Procedure R-9 (NSI)
Verification R-6 R-3 70312R Preoperational Testing Procedure (IISl/TMI)
R-6 R-3 R-1 Witness 70313R Witness Containment Leak Rate (IISl/TMI)
Test R-6 R-3 R-1 70314R Witness Integrated Hot Functional (ilSl/Tiil)
Test R-3 R-2 R
70315R (f4Sl/Till)
Witness ESF R-6 R-3 R-1 70316R Witness Loss of Offsite (NS1/ Tlil)
Power R-6 R-3 R-1 7031'/R (NSl/TMI)
Witness RPS R-6 R-3 R-1
INSPECTION PROCEDURES - TMI-l RESTART PHASE Procedure Number May be Must be Must be (Assignuent)
Ti tle Started Started Complete 70320R (NSI)
Evaluation of Test Results R-6 R-3 R-1 70322R (NSl)
Evaluation of Test Results - ESF R-6 R-3 R-1 Evaluation of Test Results -
70323R Containment Leak Rate (NSl)
Testing R-6 R-1 R-1 70324R Evaluation of Test Results -
(NS1)
Integrated Hot Functional Testing R-3 R-1 R
70325R (NSI)
Evaluation of Test Results - RPS R-3 R-1 R-1 70326R Evaluation of Test Results - Loss (NS1) of Offsite Power R-3 R-1 R-1 70329R Verification Tests are Evaluated
- (NSl) by Licensee R-3 R-1 R
Inspection of License and Technical 71501R Spec. compliance related to (TMI)
Startup Testing P-3 P-1 P
72400R (NS1)
Overall Startup Test Program P-6 P-3 P-1 83630R Radiation Protection - Startup (RS) and Power Ascension P-3 P-2 P-1 64530R Radioactive Waste Systems --
(RS)
Startup and Power Ascension P-3 P-2 P-1 Pre-critical Test Procedure Review 72564R (Protective Trip Circuit or Rod (NS1)
Drop Measurements)
R-6 R-3 R
Pre-critical Test Procedure Review 72566R (RCS Leak Test or Fressurizer (NSI)
_ Effectiveness)
R-6 R-3 R
Pre-critical iest Procedure 72568R Verification for Category II Test (NS1) and Unreviewed Category I Tests R-6 R-3 R
72570R Low Power Test Procedure Review (NSI)
(Initial Criticality)
R-6 R-3 R
Low Power Test Procedure Review (Mod-72572R erator Temperature Coefficient &
(NSl)
Control Rod Worth or Boron Worth &
R-6 R-3 R
Psuedo Rod Ejection Worth) 2 d
INSPECTION PROCEDURES - TMI-l RESTART PHASE Procedure Number May be Must be Must be (Assignment)
Ti tle Started Started C6mplete 72574R Low Pcwer Test Procedure (NSl)
Verification R-6 R-3 R
Power Ascension Phase Procedure 72576R Review (Natural Circulaticn or (NSI)
Power Reactivity Coefficient Measure - R-6 R-3 R
ment)
Power Ascensior Phase Procedure 72578R Review (Evaluation of Core (NS1)
Performance)
R-6 R-3 R
Power Ascension Phase Procedure 72580R Review (Turbine Trip or Generator (NSI)
Trip)
R-6 R-3 R
Power Ascension Phase Procedure 72582R Review (Shutdown from Outside~Contro l (NS1)
Room or Loss of Offsite Power)
R-6 R-3 R
Power Ascension Procedure Review 72584R (Evaluation of Flux Asymmetry or (NS1)
Psuedo Rod Ejection Test)
R-6 R-3 R
72586R Power Ascension Phase Procedure (NS1)
Verification R-6 R-3 R
72592R Inspector Witness of Criticality (HSl/THI)
T
/Zb2dK Inspector Witness of Power (NSl/IMI)
Ascension Testing I
P 72330R Inspector Witness of a (NSl/TMI)
Transient Test T
P 72598R (NS1)
Low Power Level Data Review D
P-2 P
72608R Power Level Plateau Data Review -
(NS1) 50%
D P-1 P
72612R (NSI)
Review Test Data - 50%
D P-1 P
72624R Power Level Data Review - 100%
(NSl) 100%
D P
P 77628P (NS1)
Review Test Data - 100%
D P
P 3
~
. ~ _ _
INSPECTION PLAN - TMI-I RESTART MODIFICATIONS l
NRC ORDER INSPECTION PROCEDURES I
ITEM DESCRIPTION
~ 37701B 55700B0 57700B0 63700B0 72701B i
l A.
N C REQUIRED MODIFICATIONS - COMPLETE PRIOR TO RESTART 4
1(a)(1)
EFW Auto Start (see 8/2.1.7.a below)
X X
1(a)(2)
EFW Control Valves (EF-V-30A/B)-Fail Open X
X X
J-1(a)(3)
Motor-Driven EFW Pumps Block Loading on Diesel X
X 1(a)(5)
EFW Flow Indication-(see 8/2.1.7.b below)
X X
X X
1(a)(8)
Control Room Annunciation for EFW Auto Start X
_X t
l 1(c)
Reactor Trip / Turbine Trip (Control Grade)
X X
2/IEB 79-05A
?
4 Item 6 Containment Isolation (see 8/2.1.4 below)
X X
2/IEB 79-05B i
Item 3 PORV Setpoint X
X j
High Pressure Scram Setpoint X
X i
2/IEB 79-05B Item S Reactor Trip / Turbine Trip (Safety Grade)
X X
2/IEB 79-05C Long Submit Design:
l Term 1 Auto Tripping of Operating RCPs X
X 1
{
TMI-l/THI-2 Separation j
4 Reactor Coolant Sampling (TMI-2)
X X
X X
X l
4 Stack Monitor - Shielding X
4 Fuel Handling Building / Ventilation X
X X-4' 8 (NUREG 0578) 2.1.1 Pressurizer Heater-Alt. Power Supply X
X X-2.1. 3.a, PORV/ Safety Valve Position Indication X
X X
X j
i Inadequate Core Cooling Instrumentation 4
2.1.3.b Incore Thermocouples X
X j
2.1.3.b RCS Saturation Margin lionitor/Tsat Alarm X
X j
2.1.3.b RCS Hot Leg / Cold Leg Temperatures X
X i
4 i
]
1 5
INSPECTION PLAN - TM1-1 RESTART MODIFICATIONS (CONT)
NRC ORDER INSPECTION PROCEDURES ITEM DESCRIPTION 37701B 55700B*
57700B*
63700B*
72701B 2.1.3.b Submit Design:
RCS Level Instrument X
X X
X-2.1.4 Containment Isolation (see 2/IEB 79-05A, Item 6)
X X
2.1.5.a Submit Design: Hydrogen Recombiner X
X X
X X
2.1.6.b Submit Design: Plant Shielding Review X
2.1.7.a EFW Auto Start (Control Grade (see 1(a)(1))
X X
i 2.1.7.b EFW Flow Indication (see 1(a)(5))
X X
X X
2.1.8.a Submit Design:
Post Accident Sampling-Containment Sump X
X X
X X
2.1.8.c Improved Iodine Instrumentation X
X Submit Design: RCS Venting X
X X
X X
2.2.2.b Onsite Technical Support Center X
X.
2.2.2.c Onsite Operational Support Center X
X l
B.
NRC REQUIRED MODIFICATIONS - COMPLETE AFTER RESTART 3 (NUREG 0578 i
Category B Recommendations) l 2.1.3.b RCS Level Instrument X
X 2.1.5.a Hydrogen Recombiner X
X 2.1.6.b Plant Shielding Mods X
X l
2.1. 7. a.
EFW Auto Start (Safety Grade)
X
-X
.2.1.8.a Post Accident Sampling X
X 2.1.8 b High Range Radiation Monitors X
X (ACRS)
Containment Pressure Monitor X
X (ACRS)
Reactor Bldg Sump Level / Water Level X
X (ACRS)
Containment Hydrogen Monitor X
X' (DENTON) RCS Venting X
X 2
E
INSPECTION PLAN - TMI-I RESTART MODIFICATIONS (CONT)
NRC ORDER IWSPECTION PROCEDURES ITEM DESCRIPTION 37701B 55700B*
57700B*
63700B*
72701B C.
OTHER MODIFICATIONS REQ'JIRING NRC APPROVAL - COMPLETE PRIOR TO RESTART Approved HPI Cross Connection (Small Break Loca)
X X
X X
X D.
OTHER MODIFICATIONS REQUIRING NRC APPROVAL - COMPLETE AFTER RESTART Auto BWST Switchover X
X X
X X
RB Spray System Upgrade / Sodium Thiosulfate Additon X
X X
X X
- Additional requirements for performing inspection procedures 557008, 577008, and 637008 may be identified and scheduled when completing 377018.
3
(.
I
PROGRAMdATIC
SUMMARY
OF OTHER NRC ORDER REQUIREMENTS NRC ORDER ITEM DESCRIPTION A.
PROCEDURES / TRAINING 1(a)(6)
EFW Available and Properly Applied When Required 1(a)(7)
EFW Availability During Surveillance Testing 1(b)
EFW Operating Procedures Independent of ICS 1(d)
Potential Small Breaks - Operator Instructions 2
IEB 79-05A Item 3 Transient / Accident Actions Regarding Voids Item 4.d Parameter Indications In Evaluating Plant Conditions Item 5 EFW and Safety-Related Valve Positions and Positioning Item 9 Rad Gas / Liquid Transfer Systems Out of Containment Item 10 System Operability Verification During Maintenance / Test IEB 79-05B ltem 1 Natural Circulation Operation Item 2 Operator Override of ESF and HPI Actuation on Low Pressure Item 4 Manual Reactor Trip for RCS Pressure Increasing Transients Item 6 Prompt Reporting Procedures for NRC Notification IEB 79-05C Item 1 A.
Upon Reactor Trip and HPI Initiation, Trip All Operating RCPs B.
Provide Two Licensed Operators in Control Room Item 3 New Guidelines - Operator Action Including RCP Trip Item 4 Dnergency Procedures Based on Guidelines Above Item 5 Inadequate Core Cooling Guidelines and Procedures (ref. 2.1.9 of flVREG-0578)/RCP Restart 4
Rad Liquid Transfer Line Isolation 8-NUREG 0578 2.1.2 Relief and Safety Valve Testing Program Description 2.1.3.b ICC Procedures 2.1.5.c Recombiner Procedures 2.1.8.a Post Accident Sampling 2.2.1.a Shift Supervisor Responsibilities 2.2.1.b Shift Technical Advisor 2.2.1.c Shift Turnover Procedures 2.2.2.a Control Room Access Control 2.1.9 Small Break LOCA Procedures (12/31/79)
Inadequate Core Cooling Procedures (Jan 1980)
Accident and Transient Emergency Procedures (Mid 1980)
Additional Concerns 3-NUREG 0578
'CXTYG0RY B RECOMMENDATIONS
~
2.2.1.b Shift Technical Advisor Training 1
r-1 b
PROGRAMMATIC
SUMMARY
OF OTHER NRC ORDER REQUIREMENTS (CONT)
NRC ORDER ITEM DESCRIPTION B.
VALVE VERIFICATION AND SYSTEM INTEGRITY
- 2. IEB 79-05A Item 5 Safety-Related Valve Positions'and Positioning Item 6 Containment Isolation (Auto) Valve Positions Item 7 EFW Valve Positions 8-NUREG 0578 2.1.6.a Systems Integrity for High Radioactivity A.
Immediate Leak Reducation Program B.
PM Program C.
TECHNICAL SPECIFICATION REVISIONS 1(a)(4)
EFW Flow Path LC0 2/IEB 79-05A Item 8
-EFW Flow Path LC0 2/IEB 79-058 Item 3 High Pressure Scram Setpoint 2/IEB 79-058 Item 7 NRC Notification / Communications D.
RADWASTE 4
TMI-I/TMI-2 Radwaste, Ventilation and Sampling Separation 5
Waste Management Capability E.
ORGANIZATION AND STAFFING 6
Managerial Capability and Resources
--Adequacy of Safety Review and Advisory Groups
--Management and Technical Capability and Training of Operations Staff
--Adequacy of Operational QA Program
--Adequacy of Facility Procedures
--Capability of Support Organizations, e.g., Health Physics and Plant Maintenance l
8-NUREG 0578 2.2.1.a Shift Supervisor Responsibilities 2.2.1.b Shift Technical Advisor 2
c-e PROGRAMMATIC
SUMMARY
OF OTHER NRC ORDER REQUIREMENTS'(CONT)
NRC ORDER ITEM DESCRIPTION F.
EMERGENCY PLANNING 3(b)
Emergency Operations' Center for Federal, State and Local
' Officials.
(Primary _and Alternate Locations)
'3(c)
Offsite Monitoring Capability, Including TLDs or Equivalent-3(e)
Test Exercise of Dnergency Plan 2.2.2.b Onsite Technical Support Center 2.2.2.c Onsite Operational Support Center Addi tional Concerns 4
Improve Emergency Preparedness
--Modify Plans W.R.T. Changing Capabilities of. Plant Instrumentation-
--Extend Capability to 10 Miles 3