IR 05000387/1989004
| ML17156B085 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/15/1989 |
| From: | Conte R, Easlick T, Walker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17156B084 | List: |
| References | |
| 50-387-89-04, 50-387-89-4, 50-388-89-04, 50-388-89-4, IEB-88-007, IEB-88-7, NUDOCS 8903310230 | |
| Download: ML17156B085 (5) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION Report Nos.
50-387/89-04 50-388/89-04 License Nos.
NPF-14 NPF-22 Licensee:
Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown Penn syl vani a 18101 Facility Name:
Susquehanna Unit 1 and Unit 2 Inspection at:
Berwick, Pennsylvania Inspection conducted:
January 23 - January 26, 1989 Inspectors:
Approved by:
-G~ g~
T.
W ker, Senior Operations Engineer E
ick, Operations Engineer R.
Con
, Chief, BWR Operations Section
~/; ~d)
Date Date J/is iD'ate Summary:
Inspection on January
January 26, 1989 (Report Nos.
50-378/89-04 and 50-388/89-04)
Areas Inspected:
A routine, unannounced safety inspection was conducted to inspect the Susquehanna Licensed Operator Training (Requalification Training)
to evaluate the effectiveness of the licensee's program.
The inspection also verified the licensee's implementation of the requested actions NRC Bulletins 88-07 and 88-07 Supplement 1 related to the LaSalle
"Power Osci llations" event.
The inspection consisted of reviews of training records and training program procedures, and interviews with licensed operators and training personnel.
. Results:
No violations or deviations were identified with the licensee's Licensed Operator Training Program.
Results of interviews with members of the operations staff indicated that the licensed operators believed that the requalification training program is valuable in training them to perform job-related activities.
Results of the inspection indicated that the licensee has fully implemented NRC Bulletins 88-07 and 88-07 Supplement 1 with respect to procedures and operator training.
8'P033i 0230 8903i7 PDR ADOCK 05000387
PNU
DETAILS 1.0 PERSONS CONTACTED Penns lvania Power
& Li ht Com an J. Blakeslee, Assistant Superintendent of Plant H. Palmer, Supervisor of Operations T. Markowski, Operations Dayshift Supervisor K. Roush, Nuclear Instruction Supervisor R. Peal, Operations Training Supervisor W. Lowthert, Manager Nuclear Training G. Fetterman, Training Document Control Specialist J.
Hackenberg, Operations Shift Supervisor J.
Seek, Simulator Instructor The inspectors also interviewed other licensed operators during the inspection period.
1.2 U.S.
NUCLEAR REGULATORY COMMISSION T. Walker, Senior Operations Engineer T. Easlick, Operations Engineer J. Stair, Resident Inspector Denotes those present at the exit meeting conducted 1/26/89
'I 2.0 LICENSED OPERATOR TRAINING PROGRAM 2.1 Licensed 0 erator Trainin Procedure Licensed Operator Requalification Program-Implementation Procedure, NPT-gA-31.2 (9/9/88)
was reviewed to ensure it met the requirements of 10 CFR 55.59(c),
which defines the requalification program.
As specified in
CFR 55.59(c)( 1), Susquehanna has established a
continuing training program which covers a two year period divided into two annual schedules of eight cycles each.
The cycles consist of preplanned lectures, simulator/JPM exercises and evaluation periods.
All classes are mandatory and makeup lectures can be viewed on video tape if necessary.
Individuals are required to successfully complete all cycle quizzes and both annual examinations.
Shift Technical advisors, although not licensed, are required to partic-ipate in all facets of requalification, with the exception of the annual examination.
The annual examinations are administered under the supervision of the Nuclear Operations Training Supervisor, following the format of the NRC administered requalification examination Procedure NTP-QA-31.2 incorporates an "Operator License Renewal Approval" form which is reviewed and signed by members of the training and operations staff, as well as the plant superintendent, to ensure each individual has satisfactorily completed the requali-fication training program.
This form is required to be completed before the application for renewal (NRC Form 398) is submitted.
It was determined that the SSES licensed operator training program, as defined in NTP-QA-31.2, meets the requirements of 10 CFR 55.59(c).
2.2 Licensed 0 erator Trainin Documentation The inspectors reviewed the operator training files for two complete operating crews and three staff licenses.
Training records for eight Senior Reactor Operator (SRO)
and eight Reactor Operator (RO) were reviewed.
The records were cross referenced with the training department's computer tracking system and were found to be complete.
Attendance, control manipulations, and makeup classes and quizzes were verified.
In discussions with the Requalification Coordinator, the computer generated reports were found to be a valuable asset in the maintenance of training records.
Copies of the cycle quizzes and annual examinations were contained in each of the files.
The documentation of training was found to be adequate.
2.3 Licensed 0 erator Interviews Interviews were conducted with four licensed Senior Reactor Operators (SRO), five licensed Reactor Operators (RO),
and members of the training staff.
It was determined that requalification training is being conducted in accordance with NTP-QA-31.2.
In the operators'pinion, the quality of training and the overall requalification program has improved in the last two years.
The new examination process was viewed as a fair evaluation of the operators'bility to perform job-related activities.
The operators are receiving training on the new testing format.
In all cases the licensed operators felt the Job Performance Measures (JPM'S) were extremely useful, in that they allow them to refresh their "in-plant" knowledge.
There was a concern with the "static-simulator" portion of the requalification examinations.
A number of operators felt that the questions asked on this portion of the examination did not require a
simulator in order to answer them.
This concern was also identified by the NRC examiners who reviewed the material for the NRC administered requalification examinations.
As a result for the NRC administered requalification examination (NRC Examination Report No.
50-387/89-13),
the licensee rewrote certain static simulator questions to be more appropriately answered on a static simulato Communications between the training and operations departments was found to be a program strength.
At the end of each cycle, a meeting between shift supervision and training instructors is held to provide input from the licensed operators to the training department.
The licensee has also instituted an exchange program in which instructors and on-shift SROs swap functions for an 18 month period.
These initiatives provide a means for communications between operations and training departments so that important topics relative to events and problems that occur on shift can be incorporated into the training program.
For example, special training was provided to the operators on the operation of the feedwater system following a recent feedwater transient that caused a plant trip.
3.0 IMPLEMENTATION OF NRC BULLETINS 88-07 AND 88-07 SUPPLEMENT
An inspection was conducted to verify the licensee's implementation of NRC Bulletins 88-07 and 88-07 Supplement 1, "Power Oscillations in Boiling Water Reactors".
The requested actions of NRC Bulletin 88-07 as documented in licensee's response letter dated October 31, 1988 were verified complete.
The requested actions of NRC Bulletin 88-07, Supplement 1 were reviewed and found to be adequate.
3. 1 Licensed 0 erator Trainin The inspectors interviewed operators and training staff with regard to the 3/9/88 event at LaSalle Unit 2 and its impact on Susquehanna operations.
Training on the LaSalle event was initially conducted by Reactor Engineering and presented to all operating crews.
Subsequent training was incorporated into the requalification program.
The lesson plans were reviewed and were determined to adequately address uncontrolled power oscillations.
All operators interviewed were thoroughly familiar with the LaSalle event and susceptibility of the Susquehanna plant to this problem.
3.2 Procedures Operating Procedures (OP), Off-Normal Procedures (ON) and General Operating Procedures (GO) were reviewed by the licensee and updated to provide operators with methods of recognizing and dealing with power osci llations.
An additional ON ("Core Flux Osci llations" ON-178-002)
was developed, which specifies actions required to reduce potential for fuel damage resulting from uncontrolled power osci llations.
Further procedure review is currently being conducted to determine if any additional changes are required to address power oscillations.
The inspectors reviewed the applicable procedures and verified that they provide for prompt corrective action.to terminate power osci llations.
The licensee's procedures address power osci llations in conditions of two loop, single loop and natural circulatio The plant simulator was utilized to walk-through the procedures that detect and mitigate uncontrolled power oscillations.
These procedures and the associated training were deterimined to be adequate to detect and terminate power osci llations.
4.0 EXIT INTERVIEW The inspection scope and findings as detailed in this report were summarized on January 26, 1989, during an exit interview with licensee personnel (see paragraph 1.0 for attendees).
The inspectors determined that no proprietary information was utilized during the inspection.