ML20198B105
| ML20198B105 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/09/1998 |
| From: | Eselgroth P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Langenbach J GENERAL PUBLIC UTILITIES CORP. |
| References | |
| NUDOCS 9812180057 | |
| Download: ML20198B105 (12) | |
Text
_ _ _._
f
+4 December 9,1998 i
Mr. J. Langenbach
.Vice President and Director GPU Nuclear, Inc.
L
. Three Mile Island Nuclear Station j
P. O. Box 480 Middletown, Pennsylvania. 17057-0480 l
l.
SUBJECT:
Mid Year Inspection Resource Planning Meeting - THREE MILE ISLAND
Dear Mr. Langenbach:
On November 10,1998, the NRC staff held an inspection resource planning meeting l
(IRPM). The IRPM provided a coordinated mechanism for Region I to adjust inspection schedules, as needed, prior to the conclusion of the Plant Performance Review cycle in l
May 1999. contains a historical listing of plant issues, referred to as the Plant issues Matrix (PIM), that were considered during this IRPM process to arrive at an integrated view of licensee performance trends. The PIM includes only items from inspection reports or other docketed correspondence between the NRC and GPU Nuclear, Inc. The IRPM may also have considered some predecisional and draft material that does not appear in the attached PIM, including observations from events and inspections that had occurred since the last NRC inspection report was issued, but had not yet received full review and '
consideration. This material will be placed in the PDR as part of the normal issuance of NRC inspection reports and other correspondence.
This letter advises you of our planned inspection effort resulting from the Three Mile Island IRPM review, it is provided to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite. Enclosure 2 details our inspection plan for the next 6 months. Resident inspections are not listed due to their ongoing and continuous nature.
We will inform you of any changes to the inspection plan, if you have any questions, please contact me at (610) 337-5234.
j Sincerely, I
Original Signed By:
Peter W. Eselgroth, Chief 9812190057 991209 Reactor Projects Branch 7 PDR ADOCK 05000289 G
PDR Division of Reactor Projects g
p 0.h Docket Nos. 50-289 l
Enclosures:
- 1) Plant issues Matrix
- 2) Inspection Plan 4 -
a
,4..
e.
a
l
- Mr. J. Langenbach 2
cc w/enet:
M. J. Ross, Director, Operations and Maintenance i
D. Smith, PDMS Manager M. Laggart, Manager, Licensing and Vendor Audits
'J.' Wetmore, Manager, Nuclear Safety and Licensing E. L. Blake, Shaw, Pittman, Potts and Trowbridge (Legal Counsel for GPUN)
- -TMI-Alert (TMIA) -
Commonwealth of Pennsylvania t
H El' t
Mr. J. Lang:nbich 3
Distribution w/ encl:
Region i Docket Room (with concurrencers Nuclear Safety Information Center (NSIC)
PUBLIC NRC Resident inspector H. Miller, RA/W. Axelson, DRA P. Eselgroth, DRP N. Perry, DRP
' C. O'Daniell, DRP DRS Deector, Region l DRS De )uty Director, Region i M. Oprendek, DRP Distribution w/enci(VIA E-MAIL):
B. McCabe, OEDO C. Thomas, PD1-3, NRR T. Colburn, PD1-3, NRR R. Eaton, PDI-3, NRR S. Weiss, NRR L.Thonus,NRR R. Correia, NRR DOCDESK Inspection Program Branch, NRR (IPAS)
DOCUMENT NAME: G:\\ BRANCH 7\\PPR\\STD-IRPM.TMI Ta receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure
- E' = Copy with attachment / enclosure "N'=
No copy OFFICE Rl/DRP
/ Rl/D,RP, 6
/
l NAME NPerry g F@
DATE 12/08/98 12/9/98 12/ /98 12/ /98 12/ /98 OFFICIAL RECORD COPY
THREE MILE ISLAND 1 PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 9/4/98 Positive IR 98-03 N
1 -OPS 3A The control room staff performed properly following identification of a plant 500 5A process computer printer problem that resulted in hourly core power distribution limits not being printed for several hours on April 29,1998. GPUN complied with the applicable technical specifications and appropriately conducted a hand calculation of power distribution limits using the minimum incore detectors.
9/4/98 Positive IR 98-03 N
1 -OPS 3A Plant operators and management responded well to a failed once through steam 499 generator (OTSG) feedwater start-up flow control valve controller, to indications of a possible leaking OTSG tube plug, in preparation for maintenance on a letdown isolation valve, and in identification of a degraded nuclear river water system pump strainer.
9/4/98 Negative IR 98-03 N
1 -OPS 2A GPUN had an effective program for controlling flood preparations using an 498 4A emergency procedure. Plant equipment was staged and ready for use if a flooding condition occurred. However, concerns were identified with the condition of and the design basis controls for the reactor building to tendon gallery flood seal. URI 98-03-01 9/4/98 Negative IR 98-03 N
1 -OPS 2A General plant housekeeping was good, with some noted improvements in the 497 emergency diesel generator areas. However, the housekeeping in the tendon access gallery was poor.
9/4/98 Positive IR 98-03 N
1-OPS 1A Control room operators performed routine tasks well. Operators were 496 3A knowledgeable of plant conditions and the reason; for annunciated alarms.
6/22/98 NCV IR 98-02 L
1 -OPS 2A GPUN properly identified, reported, and took corrective actions following a 484 Positive NCV 98 SA situation where both trains of the reactor building spray system were unavailable l
LER O2 5B due to a problem with a control room push-button for one train while the other LER 98-004 SC train was removed from service for surveillance testing; violation of technical specifications. (Enforcement Discretion per Vll.B.1 of the Enforcement Policy) 1 of 8
THREE MILE ISLAND 1 PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 6/22/98 Negative IR 98-02 N
1-OPS 2B While all Technical Specification (TS) required testing had been accomplished on 483 URI 98 5A the FHB ESF system, the routine testing did not verify that the system could 01 maintain a negative pressure on the FHB following a design basis fuel handling accident, and did not include verification of satisfactory operation of the FHB environmental enclosure. GPUN had identified these deficiencies as part of their maintenance rule sccping review. The inspectors considered this an Unresolved item, pending review of initial ESF system installation testing and GPUN documentation of the maintenance rule implementation issues.
6/22/98 Positive IR 98-02 N
1 -OPS 1A Control room discussions on the risk of maintenance items including the 482 3A emergency diesel generator (EDG) overhauls and the combined outage on the "A" traine of the decay heat removal (DR), decay heat river (DH), and reactor building spray (BS) systems were good.
9/4/98 Negative IR 98-03 N
2-3A No missed post-maintenance test (PMT) activities were identified in a detailed 503 MAINT review of three safety-related work packages. However, several identified weaknesses indicated the need for continued improvement in the documentation of PMT activities and verification that job order PMT sheets and instructions, maintenance procedure instructions, and surveillance tests meet requirements.
9/4/98 Positive IR 98-03 N
2-3A Observed surveillance test activities were conducted well, including emergency 502 MAINT safeguards, reactor protection, and undervoltage re!ay testing.
9/4/98 Positive IR 98-03 N
2-3A GPU maintenance department personnel performed well during the observed 501 MAINT activities over the period. This included verification of several work packages and observation of good procedural usage. Niaintenance activities on a nuclear closed cooling heat exchanger showed that it was in good condition. Work to correct a body-to-bonnet leak on the letdown isolation valve to the reactor coolant bleed tanks was very well coordinated and went very smoothly.
9/4/98 Negative IR 98-03 N
3-ENG SA Severalissues were identified dealing with the controls in place to document, 506 58 track, and assess identified reactor building tendon grease leakage, both from end caps on horizonta! tendons and through concrete cracks at the lower portion of the vertical tendons. IFl 98-03-03 2 of 8
v THREE MILE ISLAND 1 PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 9/4/98 Negative IR 98-03 N
3-ENG 4A The emergency feedwater (EFW) system was operable based on review of 505 calculations and testing, assuming that the October 1997 new design basis accident calculation was correct. However, the UFSAR Chapter 14 LOFW design basis accident analysis for the EFW system had not been well maintained. The calculation process was weak in that a design basis calculation did not require a safety evaluation once the design verification of the information had been completed. The safety determination process, used to justify a temporary procedure change to allow a lower EFW capacity test flowrate to depressurized OTSGs, was inadequate. Further, recent changes to the design basis in October 1997 had not been translated into a PFU which would have informed other GPUN employees that there was a new design basis calculation. URI 98-03-02 9/4/98 Positive IR 98-03 N
3-ENG 4B Engineering support to plant operation continued to be strong, this included good 504 support to operations in response to equipment problems.
6/29/98 Negative IR 98-04 N
3-ENG 4A One minor violation was identified in that Table 9.3-1 of the updated final safety 495 analysis report did not accurately reflect the actual plant operating conditions for the intermediate closed cooling water system. Appropriate corrective actions have been taken to ensure that the UFSAR is updated to accurately reflect normal plant operating conditions.
6/29/98 Positive IR 98-04 N
3-ENG 3A The expert panel had performed its assigned functions in accordance with program 494 procedures in an appropriate manner. The expert panel's decisions were appropriate regarding implementation of maintenance rule requirements.
6/29/98 Strength IR 98-04 N
3-ENG 3B The process and knowledge of personnel assessing risk before taking equipment 493 5C out-of-service was acceptable. Also, the recently completed periodic assessment met all of the maintenance rule (a)(3) requirements. Identified weaknesses were being appropriately addressed by the licensee.
6/29/98 Strength IR 98-04 N
3-ENG 3B Expert panel members, licensed operators, managers, and system engineers were 492 fully aware of their responsibilities regarding maintenance rule requirements during normal operations and emergent work situations. Their understanding of rul? was acceptable. Lotus Notes was an excellent tool with which the system engineers i
were well versed and effectively used to monitor and trend the performance of
)
their responsible systems.
l 3 of 8
THREE MILE ISLAND 1 PLANT ISSUES MATRIX Date Type Source ID SFA Co<fe item Description 6/29/98 Strength IR 98-04 N
3-ENG SA Licensee initiated audits and self assessments of the maintenance rule program 491 5B requirements were broad based and effective. Significant improvements in the 5C implementation of the program were noted.
6/29/98 Strength IR 98-04 N
3-ENG 4C The establishment of SSC risk significance was deemed acceptable. The primary 490 use of the TMI-1 NOHUMAN model for SSC importance measure evaluation was not consistent with the intended methodology, as suggested in NUMARC 93-01, however, all SSCs were determined to have been appropriately ranked in regard to risk. The licensee's establishment of performance criteria for (a)(2) SSCs was also acceptable. The team viewed the licensee's use of two awareness levels for SSC unavailability to be good.
6/29/98 Weaknes IR 98-04 L
3-ENG 3A Industry operating experience (IOE) had been incorporated into the maintenance 489 s
4B program, and was being used to establish goals and improve system performance.
However, it was noted that, administratively, several system engineers were slow in the closure of IOE review assignments. Licensee personnel had previously identified this area of weakness and had recently instituted measures to correct this concern.
6/29/98 Strength IR 98-04 N
3-ENG 3B The system engineers were very knowledgeable of the maintenance rule and 488 4C appropriately maintained an acute awareness of their system responsibilities.
I Lotus Notes was an excellent tool with which the system engineers were well versed and effectively used to monitor and trend the performance of their responsible systems.
6/29/98 Strength IR 98-04 N
3-ENG 4C Appropriate goal setting and monitoring was in place for those SSCs that were in 487 an (a)I1) status. Corrective and preventive maintenance was appropriate and effective for those SSCs in an (a)(2) status.
6/29/98 Strength IR 98-04 N
3-ENG 4C All structures, systems, and components (SSCs) were appropriately identified and 486 included within the scope of the maintenance rule. For those SSCs that were excluded from the scope of the rule, justification was found to be correct and complete.
4 of 8
THREE MILE ISLAND 1 PLANT ISSUES MATRIX Date Type Source ID SFA Code item Description 6/22/98 Licensin IR 98-02 N
3-ENG 2A The NRC staff and GPUN discussed the makeup system suction configuration, 485 g
4A after GPUN identified that it was different than as stated in an NRC generic safety evaluation for B&W plants. Specifically, the suction cross-tie valves at TMl are open, although the NRC evaluation stated that they were shut. The NRC staff remained concerned that the opening of the cross ties would allow the third pump to potentially be affected by an unknown makeup tank low level condition. This an inspector follow item, pending additional review.
9/4/98 Positive IR 98-03 N
4-PS SA Radioactive waste quality assurance activities were generally effective. The audit 512 performed as required by technical specifications was extensive in scope and depth.
9/4/98 Positive IR 98-03 N
4-PS SA Self-assessments by the radiological controls group in the area of radiologica!
511 SC controls for radioactive materials, contamination, surveys, and monitoring were normally good and provided recommendations and appropriate corrective actions for identified deficiencies and problems.
9/4/98 Positive IR 98-03 N
4-PS 38 The NRC and DOT training and retraining requirements for radioactive waste group I
510 personnel were satisfied.
9/4/98 Positive IR 98-03 N
4-PS 1C The program for shipping low level radioactive waste for disposal and 509 transportation of other radioactive materials was generally effective.
9/4/98 Positive IR 98-03 N
4 oS 2A Overall, the solid radioactive waste management program was effective based on 508 2B the existence of appropriate procedures and controls, the acceptable condition of 3B facilities and equipment, and the proper implementation of the program by knowledgeable and experienced personnel.
9/4/98 Positive IR 98-03 N
4-PS 3A Overall, effective performance in the area of radiological controls for radioactive 507 materials, contamination, surveys, and monitoring was evident.
5 of 8
ABBREVIATIONS USED IN PIM TABLE AMSE American Society of Mechanical Engineers CAP Corrective Action Process CAS Central Alarm Station CF Core Flood DBD Design Basis Document DH Decay Heat DR Decay River EA EnforcementAction ECCS Emergency Core Cooling System EQ Equipment Qualification ES Emergency Safeguards GORB General Office Review Board GPUN GPU Nuc ear, Inc.
HPRB Human Performance Review Board l&C Instrument and Control IST Inservice Test j
LER Ucensee Event Report MR Maintenance Rule MU Makeup NI Nuclear Instrument NRC Nuclear Regulatory Commission NSA Nuclear Safety Assessment 6 of 8 m
m.
NSCC Nuclear Safety and Compliance Committee.
OE Opershonal Expenence OTSG' Once Through Steam Generator I
PMT-Post Maintenance Test PORV Power Operated Relief Valve PRG~
Plant Review Group RB Reactor Building -
I RBEC Reactor Building Emergency Cooler RC Radiological Controls RCP Reactor Coolant Pump RCS Reactor Coolant System RHR Residual Heat Removal RPS Reactor Protection System RR Reactor River SAS Secondary Alarm Stabon SE Safety Evaluation SFP Spent Fuel Pool SS Shift Supervisor SSCs Systems, Structures and Components TMl Three Mile Island TS Technical Specification 4
[FSAR Updated Final Safety Analysis Report 7of8 i
______.____,_____._m
w GENERAL DESCRIPTION OF PIM TABLE COLUMNS De The actual date of an event or significant issue for those items that have a clear date of occurrence (mainly LERs), the date the source of the information was issued (such as for EALs). or the last date of the inspection period (for irs).
Type The categorization of the item or finding - see the Type / Findings Type Code table, below.
Source The document that describes the findings: LER for Licensee Event Reports, EAL for Enforcement Action Letters, or IR for NRC Inspection Reports.
ID Identification of who discovered issue: N for NRC; L for Licensee; or S for Self Identifying (events).
SFA SALP Functional Area C0 ties: OPS for Operations; MAINT for Maintenance; ENG for Engineering; and PS for Plam Support.
Code Template Code - see table below.
DW@
Details of NRC findings on LERs that have safety significance (as stated in irs), findings described in IR Executive Summaries, and amplifying information conta,ned in EALs.
i TYPE / FINDINGS CODES 1
Ope.ational Performance: A - Normal Operations: B - Operations During Transients; and ED Enforcement Discretion - No Civil Penalty 2
Material Condition: A - Equipment Condition or B - Programs and Processes Strength Overall Strong Licensee Performance Weakness Overall Weak Licensee Performance 3
Human Performance: A - Work Performance; B - Knowledge, Skills, and Abilities /
Training; C -Work Environment eel
- Escalated Enforcement item -Waiting Final NRC Action
- 9" 9"
"9 "
9 9"* ""
VIO Violation LevelI,11,111, or IV NCV Non-Cited Violation 5
Problem Identification and Resolution: A - Identification; B - Analysis; and C - Resolution DEV Deviation from Licensee Commitment to NRC NOTES:
Positive Individual Good Inspection Finding Eels are apparent violations of NRC requirements that are being considered for escalated enforcement action in accordance with the " General Statement of Policy and Negative Individual Poor inspection Finding Procedure for NRC Enforcement Action * (Enforcement Policy), NUREG-1600.
However, the NRC has not reached its final enforcement decision on the issues LER Licensee Event Repo;t to the NRC identified by the Eels and the PIM entries may be modified when the final decisions are URI "
Unresolved item from inspection Report made. Before the NRC makes its enforcement decision, the licensee will be provided with an opportunity to either (1) respond to the apparent violation or (2) request a Licensing Licensing issue from NRR predecisional enforcement conference.
MISC Miscellaneous - Emergency Preparedness Finding (EP).
URis are unresolved items about which more information is required to determine Declared Emergency, Nonconformance usue, etc. The whether the issue in question is an acceptable item, a deviation, a nonconformance, or type of at,VISC findings are to be put in the item a violation. However, the NRC has not reached its final conclusions on the issues, and Description column.
the PIM entries may be modified when the final conclusions are made.
TEMPLATE CODES
._____________j
Enclosur@ 2 THREE MILE ISLAND INSPECTION PLAN FOR DECEMBER 1998 THROUGH MAY 1999 inspection No.
Program AreafTitle Planned Dates Type ins h
Tl 2515/138 Operator Workarounds 12/14/1998 2
Si iP 37550,40500 Engineering 5/10/1999 3
Core IP 64704 Fire Protection Program 5/31/1999 1
- Core Legend:
IP Inspection Procedure Number Tl Temporary Instruction Program / Sequence Number Core Minimum NRC Inspection Program (mandatory at all plants)
OA Otherinspection Activity RI Additional Inspection Effort Planned by Region i SI Safety Initiative inspection
-