IR 05000445/1989045
| ML20247E580 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/21/1989 |
| From: | Bitter S, Burris S, Joel Wiebe Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247E570 | List: |
| References | |
| 50-445-89-45, 50-446-89-45, NUDOCS 8907260224 | |
| Download: ML20247E580 (14) | |
Text
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., . U. 5. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION NRC Inspection Report: 50-445/89-45 Permits: CPPR-126 50-446/89-45 CPPR-127 Dockets:'50-445 Category: A2 50-446 Construction Permit Expiration Date: Unit 1: August 1, 1991 Unit 2: August 1, 1992 Applicant: TU Electric Skyway Tower 400 North Olive Street Lock Box 81 Dallas, Texas 75201 Facility Name: Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 Inspection At: Comanche Peak Site, Glen Rose, Texas Inspection Conducted: June 7 through July 5, 1989 '6bl h 1/2t/54 Inspector: S. E. Bitter," Resident Inspector, [Dhte Operations Inspector: ff S. P. Burris, Senior Resident Inspector, / Tate Operations Reviewed by: _rd N
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I u. S. Wiebe, Senior Project Inspector / Ddte ) ps!"uste EEj!p D L______..__________ __ ___ ____ ______ __ __ __. _ ________ ___ _______ ___ _____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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t Inspection Summary Inspection Conducted: June 7 through July 5, 1989 (Report 50-445/89-45; 50-446/89-45) Areas _ Inspected: Unannounced resident safety inspection of applicant action on previous inspection findings, preoperational retest procedure review, preoperational test witnessing, plant-tours, operational staffing, and relicensing review of training and qualification programs.
Results: Within the areas inspected, a weakness in the quality of reoperation procedures was noted.
This was identified as an:open item (paragraph 3).
In. addition, continued problems with procedure compliance during conduct of testing is apparent.
Two other open items were identified.
One concerned t.he applicant's program for ensuring that temporary and mobile-permanent equipment does not impact the operability of safety-related equipment (paragraph 5).
The other concerned' human factors considerations for the diesel generator alarm panel (paragraph 5).
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DETAILS 1.
Persons Contacted
- M.
R. Blevins, Manager of Nuclear Operations Support, TU Electric
- H.
D.-Bruner, Senior Vice President, TU Electric
- W.
J. Cahill, Executive Vice President, Nuclear, TU Electric
- W. G. Counsil, Vice Chairman, Nuclear, TU Electric
- G.
G. Davis, Nuclear Operations Inspection Report Item Coordinator, TU Electric
- J -. Greene, Site Licensing, TU Electric
- W.
G. Guldemond, Manager of Site Licensing, TU Electric
- T.
L. Heatherly, Licensing Compliance Engincar, TU Electric
- J.
C. Hicks, Licensing Compliance Manager, TU Electric
- C.
B. Hogg, Chief Manager, TU Electric
- D. M. McAfee, Manager, QA, TU Electric
- E.
F. Ottney, Program Manager, CASE
- S.
5. Palmer, Project Manager, TU Electric
- A.
B. Scott, Vice President, Nuclear Operations, TU Electric
- J.
F. Streeter, Director, QA, TU Electric The NRC inspector also interviewed other applicant employees during this inspection period.
- Denotes personnel present at the July 5, 1989, exit interview.
2.
Applicant Action on Previous Inspection Findings (92702) (Closed) Open Item (445/8917-0-10): " Traceability of Test Equipment."
This item stemmed from an NRC inspector's observation that in some cases, where multiple, identical test instruments are being used simultaneously, no records that tie a particular instrument to a particular function are maintained.
The applicant explained that in the instances observed by the
inspector, the test instruments were not being used for the ' quantitative recording of data; instead, they were used for recording qualitative data (continuity).
Therefore, there is no reason to tie a given instrument to a particular function.
The inspector is satisfied with the applicant's response and has no further questions.
This item is closed.
I 3.
Preoperational Retest Procedure Review (70700, 70304, 70341) The inspector reviewed the following tests to verify that the procedure format and style is adequate for clarity and ease of use and to verify that the procedure is technically correct.
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a.
Procedure 1CP-PT-64-10 SFT, " Safeguards Actuation Relay Test," Revision O.
The following problems were noted: (1) When verifying that relay contacts are open, the procedure, in the notes to Data Sheet 1, Iequires momentarily connecting a multimeter between specified terminals.
The inspector was concerned that unless continuity from the multimeter to the contacts is first verified, this method has an unacceptably high potential for error.
The applicant has indicated that the intent of the procedure is to connect the multimeter and leave it connected when the action to change the. state of the contacts is implemented.
The continuity of the connection is therefore verified when the specified contacts are shut.
The applicant agreed to clarify the procedure to reflect the intent.
The inspector had no further questions about this issue.
(2) There were several administrative errors in the procedure.
For example, in Step 7.1.1.6 the component I.D. number for contacts 11-12 is listed as MCC-1EB1-2 on Data Sheet 2, while on Table I, it is listed as MCC-2EB1-2.
In addition, pages 134 through 146 indicate that the total number of pages is 242 while the rest correctly indicate that the tota? number of pages is 243.
The applicant agreed to correct the discrepancies, b.
Procedure 1CP-PT-29-03 RT-3, " Diesel Generator Load Test Retest 3," Revision 1.
The following problems were noted: (1) There are several errors in the procedure which result in reference to instrumentation, data sheets, or actions in the wrong train.
For example Steps 6.1.25 (Train A) and 6e2.25 (Train B) . both refer to both Data Sheets 9 and 10.
Train A readings should only be taken on Data Sheet 9 and Train B readings on Data Sheet 10.
Train B prerequisite Steps 6.2.5, 6.2.6, . 6.2.8.3, 6.2.9, 6.2.10, 6.2.11, and 6.2.18 should refer to Section 7.2 instead of 7.1 (The Train A section).
Step 7.2.3.4 should refer to the 1DG2 diesel . instead of the 1DG1 diesel.
Step 7.2.21.5 should record Train B data on . Data Sheet 6 instead of Data Sheet 5.
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1 Table II, page 3 of 6 lists Train A l instrumentation nunbers for Station Service l Water flow and temperature instead of Train B I ' instrumentation.
(2) There is no page 3 of 3 for Data Sheet 5.
(3) Data Sheet 4, page 6 of 12, lists an incorrect gauge.
number for "Diff Press Lube Oil" instead of the , correct number (1-PI-3412-2B).
(4') The NOTE following Step 7.1.18 references Step 7.3.1 which refers to Attachment 1.
At this point in the test procedure the diesel generator is already running however, Attachment 1 includes actions to be performed prior to the diesel generator run.
It appears that Step 6.1.25 should also reference Attachment 1 to identify those actions to be performed prior to the diesel generator run.
The applicant agreed to correct the identified items.
The inspector notes that approximately half of the identified items were identified and corrected by applicant in Revision 2 to 1CP-PT-29-03 RT-3.
Some of the remainder were corrected by a temporary change notice '(TCN) during the conduct of the test.
In several cases, the' test was continued even when the test procedure could not be complied with.
The applicant verified by discussions with test personnel that the test was conducted in an acceptable manner and the procedure subsequently changed to refleet the actual conduct of the test.
No violations of NRC requirements were identified; however, the errors identified in a.(2), b.(1), b.(2), b.(3), and b.(4) indicates inattention to detail by procedure writers and reviewers.
This is identified as an open item pending applicant action to correct this inattention to detail and subsequent NRC verification that issued procedures have fewer errors (445/8945-O-01).
I 4.
Preoperational Test Witnessina (704411 The inspector witnessed selected portions of Preoperational Tests 1CP-PT-29-02 RT-3, " Diesel Generator Control Circuit Functional and Start Test Retest 3," and 1CP-PT-29-03 RT-3, " Diesel Generator Load Test Retest 3."
The personnel conducting the tests were knowledgeable concerning the tests and were aware of their duties.
Quality Assurance personnel were present for required test hold points.
Problems with the diesel generator electronic speed control were documented and resolved in accordance with administrative procedures.
The < -_ _ _-
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6 test log was detailed enough to reconstruct test events and sequence.
No problems were identified.
, 5.
Plant Tours (71302) , During a' tour of the Train A diesel generator. room prior to running the diesel for a preoperational test, the inspector noted the following:- A temporary hoist was suspended above the turbocharger . and the permanent hoist was suspended above the generator with the hoist chains laying on the top of the generator housing.. This item is considered open pending applicant demonstration.that a program exists for controlling. temporary hoists and the location of the permanent hoists such that they do not affect'the operability of the diesel generator during a seismic event (445/8945-0-02).
The diesel generator alarm panel does not have the row . and column numbers of alarm windows identified.
This may affect the ability of the operator to locate the applicable alarm response procedure.
This item is considered.open pending applicant labeling of the rows , 'and columns (445/8945-0-03).
6.
Operational Staffing (36301) This portion of the' inspection involved verifying t?.,e adequacy of the applicant's' organizational structure.
The NRC inspector reviewed current organizational charts and .Section 13.1 of the FSAR to verify compliance to ANSI N18.1, ANS 3.1, and Regulatory Guideline 1.8.
It was determined that all staff positions are currently filled and that those key personnel in management and supervisory positions satisfy the minimum qualification requirements.
Furthermore, the NRC inspector reviewed personnel resume records and training records to verify that those key positions requiring operator licenses have received the prerequisite training and have been licensed'(e.g., operations manager).
In addition, quality assurance / quality control organizations have been designated ' as indicated in the FSAR and the quality assurance plan.
Key quality assurance / quality control managers and supervisors meet the minimum qualifications required by their positions.
' Within the scope of this inspection, no violations or deviations were identified.
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, 7.
Relicensing Review of Training and Qualification Programs (41301) This portion of the inspection involved verifying that the applicant's proposed programs for licensed operators and nonlicensed staff training has incorporated regulatory requirements and licensee commitments.
The NRC inspector verified that the applicant has established a proposed program for new reactor operators (ROs), for upgrading ROs to senior reactor operators (SROs) licenses, and for qualifying / training instructors, shift technical advisors (STAS) and engineers for SRO licenses as required.
During the inspection, the NRC inspector reviewed the following procedures: Training Manual Procedure TRA-203, Revision 4, . " Replacement Licensee Training," dated August 26, 1985 Training Manual Procedure TRA-204, Revision 6, " Licensed . operator Requalification Training Program," dated August 15, 1988 Training Manual Procedure NOT-110, Revision 1, . " Evaluating the Effectiveness of Training," dated April 27, 1987 Training Manual Procedure NOT-112, Revision 1, " Training . Material Revision," dated January 15, 1989 Training Manual Procedure NOT-201, Revis;un 1, " Training . Department Staff Training," dated February 24, 1986 Training Manual Procedure NOT-401, Revision 2, " Training . Configuration Management Program," dated January 3, 1989 Training Manual Procedure NOT-108, Revision 3, " Lesson . Material Revision," dated June 1, 1987 The NRC inspector verified that the applicant's proposed i training program has established a system for operator license application submittals in accordance with the requirements of 10 CFR Part 55.
The applicant has established a requalification program that meets the requirements of 10 CFR Part 55.59 and incorporates training requirements derived from the knowledge and abilities catalogue, NU1'EG-1121, te.g., remote.7hutdown panel training).
The , i applicant has implemented procedures and programs to ensure that classroom and simulator training are based upon up-co-date training materials that reflect the as-built . ccadition of the plant and approved operating, abnormal, ' l emergency, and administrative procedures.
Furthermore, the applicant's training program incorporates those training i requirements imposed by NUREG-0737.
The NRC inspector i
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verified that the applicant's training program utilizes
position task analysis and establishes learning objectives that describe the desired performance.
Implementation of training is based upon stated objectives with evaluation of trainee performance.
Evaluation and revision of the training program is based upon trainee performance, course evaluation, plant events, design changes, significant operating experience reports, (SOERs), plant incident reports (PIRs), and industry events /information.
In addition, the' applicant has committed to achieving full training program accreditation within the ' required 2-year criteria following issuance of a full-power license.
This accreditation plan includes certification of the plant simulator within 1 year following full-power licensing.
The NRC inspector reviewed the individual training record packages of eight licensed operators (two unit supervisors, two shift supervisors, two SROs, and two ROs) and two STAS.
The NRC inspector verified that personnel licenses were current, records were complete, and training encompassed those critical attributes described above in 10 CFR Part 55, and NUREGs 0737, and 1121.
Furthermore, the NRC inspector verified that the applicant is presently upgrading its training program, records filing system, and is making those revisions necessary to comply with commitments made subsequent to NRC inspection (NRC Inspection Report 50-445/OL 88-01) dated July 27, 1988.
Within the scope of this inspection, no violations or deviations were identified.
8.
Open Items open items are matters which have been discussed with the applicant, which will be reviewed further by the inspector, and which involve"some action on the part of the NRC or applicant.or both.
Three open items disclosed during the inspection are discussed in paragraphs 3 and 5 (two items).
9.
Exit Meeting (30703) An exit meeting was conducted on July 5, 1989, with the applicant's representatives identified in paragraph 1 of this report.
No written material was provided to the applicant by the inspectors during this reporting period.
The applicant did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
During this meeting, the NRC inspectors summarized the scope and findings of the inspection.
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, CRITERIA FOR DETERMINING CATEGORY RATING 1.
Management Involvement in Assuring Quality.
2.
' Approach to Resolution of Technical Issues from a Safety Standpoint.
83.
Responsiveness to NRC Initiatives.
l4.- Enforcement History.
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Operational and construction Events.
6.
Staf fing (including management).
RATINGkl[Y: (For Categories 2 - Declining and 3, provide narrative basis for conclus1on)~ j Category I Category 2 - Decitning Category 2 Category 3 I Inspector (s) concerns adequately addressed E . l[[InspectionEvaluationTo ein processed.
Lead Inspector _ - 7f/IfSectionChie Mk / _(OVte) l ,- ($1gnature) (DAey ignature) - _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ }}