IR 05000382/1987014
| ML20236G253 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/27/1987 |
| From: | Jaudon J, Luehman J, Skow M, Staker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20236G251 | List: |
| References | |
| 50-382-87-14, IEIN-87-021, IEIN-87-21, NUDOCS 8708040181 | |
| Download: ML20236G253 (11) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-382/87-14 License:
NPF-38 Docket:
50-382
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Licensee:
Louisiana Power & Light Company (LP&L)
142 Delaronde Street New Orleans, Louisiana 70174 Facility Name: Waterford Steam Electric Station, Unit 3 l
Inspection At: Taft, Louisiana Inspected Conducted: June 16 through July 15, 1987
7 f/87 Inspectors: ____Jf[f
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m G. Luehmhn,~ Senior Resident Inspector D6te '
]l27/B"7
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W R.'E. Skow, Project Inspector, Reactor D' ate '
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Project Section
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T-/T-27 WR.I St'ak%W" Re'sident Inspect r Date Approved:
c2 <, z M
7 27 87 P.
, Chief D6te
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acto [aud r Pr ect Section A 8708040181 870728 PDR ADOCK 05000382 G
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Inspection Summary Inspection Conducted June 16 through July 15, 1987 (Report 50-382/87-14)
Areas Inspected:
Routine, unannounced inspection of:
(1) Followup'on Previously Identified Items, (2) Licensee Eve 11t Report Followup (3) Plant Status, (4) Monthly Maintenance, (5) Monthly Surveillance, (6) ESF System Walkdown, (7) Routine Operational Safety Inspection, (8) Natural Circulation Cooldown, (9) Onsite Review Committee, and (10) Information Notices.
Results: Within the areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted Principal Licensee Employees J. G. Dewease, Senior Vice President, Nuclear Operations
- R. P. Barkhurst,, Vice President, Nuclear Operations
- N. S. Carns, Plant Manager, Nuclear P. N. Backes, Corporate QA Manager-I S. A. Alleman, Assistant Plant Manager, Plant Technical Staff
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- J. R. McGaha, Assistant Plant Manager, Operations and Maintenance
J. N. Woods, Quality Manager, Nuclear A. S. Lockhart, Nuclear Operations Support and Assessments Manager R. F. Burski, Engineering Service Manager
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- G. E. Wuller, Onsite Licensing Coordinator T. H. Smith, Maintenance Superintendent, Nuclear
- Present at exit interview.
In addition to the above personnel, the NRC inspectors held discussions I
with various operations, engineering, technical support, maintenance, and administrative members of the licensee's staff.
2.
Unresolved Items An unresolved item is a matter about which more information is required to determine whether it is acceptable or may involve a violation or deviation.
One unresolved item was identified during this inspection and is discussed in paragraph 11.
3.
Followup of Previously Identified Items (Closed) Unresolved Item (382/8424-02), " Unqualified Components in Hydrogen Analyzers." This item related to Significant Construction Deficiency (SCD) 79.
SCD-79 was further discussed in NRC Inspection Report 50-382/84-29 and closed.
Unresolved Item 382/8424-02 is considered closed.
(Closed) Violation (382/8425-01), " Licensee Document Controls for Vendor Manuals and Technical Data." The licensee stated that vendor manuals have been placed under administrative. controls.
Procedure NSP-602, Revision 0,
" Control of Vendor Information," was reviewed and appears to provide adequate control of the vendor manuals.
Procedure MD-1-007, Revision 2
" Preventive Maintenance Task Identification," was reviewed by the NRC
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inspector and appears to provide adequate referral to vendor manuals during task identification. This item is closed.
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(Closed) Violation (382/8425-02), " Failure to Invoke Requirements in l
Maintenance Procedure for Tightening Structural Fasteners." The NRC inspector reviewed Procedure MM-6-012, Revision 1.
The procedure appears to have additional instructions such as QC hold points, snug tight I
definition, and torque wrench calibration requirements. This item is l
closed, j
(Closed) Unresolved Item (382/8435-03), " Dry Cooling Tower Fan Motor Speed Reducers." This item concerned the oil qualification for the speed l
reducers. The licensee stated that the AGMA No. 4EP oil has been replaced with Mobil SHC-629. The NRC inspector reviewed the Plant Lubrication
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Manual which listed the SHC-629 oil for the dry cooling tower fan motor I
speed reducers. The manual also referenced the Environmental Qualification of the oil and provided the oil specifications.
The SHC-629 oil appears to be satisfactory throughout the expected operating range.
This item is closed.
(Closed) Violation (382/8442-01), " Procedures for Procurement of Spare Parts
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for Safety-Related Applications." The NRC reviewed the Spare Parts i
Equivalency Evaluation Reports (SPEER) performed on some of the procurement packages discussed in NRC Inspection Report 50-382/84-42.
Other procurement packages appeared to meet documentation requirements.
l The licensee also revised Procedure UNT-8-001, " Processing of Procurement i
Documents." This procedure discussed the use of SPEERs. This item 1s
closed.
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l (Closed) Violation (382/8501-01), " Failure to Have Procedures." The j
licensee revised Procedure UNT-8-001.
Revision 12 includes references to i
FSAR Table 3.2-1, specifically includes plant structures in the safety-related requirements, and appears to assure that procurement documents reflect appropriate quality assurance requirements.
This item is closed.
l (Closed) Violation (382/8504-01), " Inadequate Documentation for l
Safety-Related Ventilatiori Heating System and Replacement Parts Used With Charcoal Filters." The licensee stated in the response to the violation, I
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dated February 14, 1986, that the safety-related parts were deleted from the purchase order and reordered separately.
The NRC inspector reviewed the purchase orders. This item is closed.
(Closed) Violation (382/8504-03), " Licensee Procedures for Maintenance of Equipment Qualification and Procurement of Spare Parts." The NRC inspector reviewed Procedure UNT-8-001, Revision 12 " Processing of Procurement Documents." The procedure appears adequate, including controls for l
SPEERs, procurement document preparation and review requirements, EQ considerations, and QA. This item is closed.
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(Closed) Open Item (382/8527-02), " Preventive Maintenance (PM) Scheduling for Replacement of S6fety-Related Components." This item concerned an automatic 25 percent extension of all PM activities and the replacement intervals of safety related devices such as Agastat relays. The licensee stated that while the program allows a 25 percent extension, the qualified life requirement is not viol 6ted. The NRC inspector reviewed the Maintenance Planning and Scheduling System Task Report.
For Agastat relays, the report noted a change out due date of about nine years from the manufactured date. The report also noted that the relays was to be changed out within ten years of the manufactured date. The NRC inspector also found similar requirements noted in Procedure ME-7-005, Revision 4,
" Time Delay Relay Setting Check, Adjustment, and Functional Test," and in Timing Relay Information Sheets. This item is closed.
(Closed) Violation (382/8527-03), " Failure to Establish Adequate Procedures." The NRC inspector reviewed the corrective action discussed by the licensee in their respor.se, dated February 14, 1986, to the violation. This included review of procedures as well as EQ Data / Records, EQ 1ask Cards, and Task Card Review Checklists.
The procedures appeared
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adequate as well as implementation as noted during review of the other i
documents. This item is closed.
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(Closed) Unresolved Item (382/8527-04), " Review of Work Package /PM task Cards." This item concerned review of work documentation by supervisors without documented EQ training. The licensee stated that line
supervisors' review is only to determine acceptability of maintenance i
performed on EQ equipment to ensure that the work instructions were i
completed, documented and acceptance criteria were adequate. The licensee
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further stated that subsequent post-maintenance reviews were conducted by engineers trained in requirements pertinent to the maintenance of
EQ equipment.
The NRC inspector reviewed selected task cards and l
EQ review checklists to verify appropriate reviews had been performed.
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This item is closed.
(Closed) Violation (382/8527-05), " Failure to Implement Procedures." This item concerned missing instructions for EQ work. The NRC inspector reviewed Procedure MI-3-323, Revision 3.
The procedure included instructions for replacing Rosemount transmitter 0-rings, lubricating the 0-ring, and torquing the cover. The item also concerned failure to perform a Spare Parts Equivalency Evaluation Request prior to use of a part. The licensee stated that the subject 0-rings were subsequently replaced during a calibration. The licensee also stated that warehouse personnel were retrained on the requirements of Procedure UNT-8-044,
" Requisition and Return of Items to Stores." The NRC inspector reviewed records to verify the replaced 0-rings and training.
This item is closed.
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(Closed) Violation (382/8633-02), " Failure to Adhere to Health Physics Procedures."
In a letter dated March 9, 1987, the licensee responded to this violation and committed, in part, to revise Procedures HP-01-101 and HP-01-110. The NRC inspector verified that these procedures had been revised as specified and implemented.
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6 (Closed) Unresolved Item (382/8701-03), " Licensee to Determine Adequacy of j
SI Drain Line Isolation." The licensee has locked these valves, and
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Procedure OP-903-031, " Containment Integrity Check," has been revised to l
reflect this change. These valves have also been added to the locked valve list of Procedure OP-100-009, " Control of Valves and Breakers."
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M violations or deviations were identified.
4.
Licensee Event Report (LER) Followup
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The W owing LERs were reviewed and closed. The NRC inspectors verified j
that reporting requirements had been met, that causes had been identified,
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that corrective actions appeared appropriate, that generic applicability had been considered, and that the LER-forms were complete. Additionally, i
l the NRC inspectors confirmed that no unreviewed safety questions were involved, and that violations of regulations or Technical Specification (TS) conditions had been identified.
(Closed)LER 382/85-23,"4160 KV Safety Related Breakers." The NRC inspector verified that operations personnel have been trained on the operation of General Electric Magne-Blast Air Circuit Breakers.
Additionally, the NRC inspecto'r verified that Procedure ME-4-131 has been l
revised to include a breaker checklist for use when racking in these l
breakers.
(Closed) LER 382/86-26, " Inadvertent Fuel Handling Building Ventilation Emergency Filtration Systen Actuation Due to Personnel Error." The NRC inspector verified that Procedure MI-3-362 has been revised to include a i
step to verify monitor identification.
(Closed)LER 382/86-27, " Fire Protection Valve Lineup Check Not Performed Due to Inadequate Procedure." This event was the subject of Violation 382/8629-02 which was reviewed and closed in NRC Inspection Report 50-382/87-07.
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(Closed)LER 382/87-16, " Reactor Trip Due to Blown Fuse in Feedwater Pump Control Circuit."
5.
f,lantStatus On July 2, 1987, at 8:48 a.m. (CDT) an unusual event was declared because of a loss of major assessment capability when both the primary and secondary meteorological monitoring instrumentation systems were found to be inoperable due to loss of both power supplies. The apparent cause was a lightning strike to both towers. After repairs to the secondary system, it was returned to service, and the unusual event ended at 7:15 p.m. on July 2.
Subsequently, the primary system was repaired and returned to service.
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The plant operated at or about full power during the enti"e inspection period.
No violations or deviations were identified.
6.
Monthly Maintenance
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Station maintenance activities affecting safety-related systems and components were observed and reviewed to ascertain that the activities were conducted in accordance with approved procedures, regulatory guides, industry codes or standards, and in conformance with TS.
Portions of the following condition identification' work authorizations (CIWA) were observed by the NRC inspectors:
l CIWA 033058 - Replacement of leaking emergency Diesel Generator Air
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l System Valve EGA-4078.
CIWA 033649 - Replace shaft and leaking 0-rfng seal in containment
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air lock outer door.
Additionally, the NRC inspector observed the performance of an engine analysis on the "A" emergency diesel generator with an EN-SPEC 1000.
No violations or deviations were identified.
7.
Monthly Surveillance The NRC inspectors observed and reviewed TS required testing and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation (LCO) were met, and that any deficiencies identified were properly reviewed and resolved.
The NRC inspector observed the performance of portions of Licensee Procedure MI-3-470, Revision 4, " Circulating Water Discharge Liquid Ef fluent Radiation Monitor Channel Functional Test PRM-IR-1900." This test was performed to meet, in part, the requirements of TS 4.3.3.10.
On July 6, 1987, the NRC inspector observed the performance of Procedure OP-903-068, " Emergency Diesel Generator Operability Verification," for the "A" Emergency Diesel Generator.
The procedure was performed to meet, in part, the requirements of TS 4.8.1.1.2.9, 4.8.1.1.2.b, and 4.8.1.2.
The NRC inspector observed portions of Procedure MI-3-101, Revision 3, "NI Linear Power Channel Calibration," (Safety Channel "A") which was performed on July 9, 1987, to satisfy the requirements of TS 4.3.1.1.(2).
No violations or deviations were identified.
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8.
ESF System Walkdown
The High Pressure Safety Injection (HPSI) system was verified operable by
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l performing a walkdown of the accessible and essential portions of the system on June 16 and 17,1987.
The NRC inspector used the Emergency Core Cooling System (ECCS) Lineup l
specified on Attachment 10.1 of Procedure OP-903-026, Revision 3, in l
conjunction with Drawing LOV-G-167.
No violations of deviations were identified.
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Routine Operational Safety Inspection By observation during the inspection period, the NRC inspectors verified that the control room manning requirements were being met.
In addition,
l the NRC inspectors observed shift turnover to verify that continuity of I
system status was maintained.
The NRC inspectors periodically questioned
shift personnel relative to their awareness of the plant conditions.
Through log review and plant tours, the NRC inspectors verified compliance with selected TS and limiting conditions for operations.
During the course of the inspection, observations relative to protected
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and vital area security were made including access controls, boundary integrity, search, escort, and badging.
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l On a regular basis, radiation work permits (RWP) were reviewed and the j
specific work activity was monitored to assure the activities were being conducted per the RWPs.
Selected radiation protection instruments were
periodically checked and equipment operability and calibration frequency
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were verified.
The NRC inspectors kept themselves informed on a daily basis of overall status of plant and of any significant safety matter related to plant operations.
Discussions were held with plant management and various members of the operations staff on a regular basis.
Selected portions of operating logs and data sheets were reviewed daily.
The NRC inspectors conducted various plant tours.and made frequent visits of the control room.
Observations included: witnessing work activities
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in progress; verifying the status of operating and standby safety systems t
and equipment; confirming valve positions, instrument and recorder readings, annunciator alarms; and housekeeping.
No violations or deviations were identified.
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10.
Natural Circulation Cooldown During this inspection period, the NRC inspector reviewed the Licensee's initiatives regarding natural circulation cooldown and prevention and mitigation of reactor vessel voiding.
In response to Generic Letter 81-21. " Natural Circulation Cooldown," the licensee stated, in a letter dated November 30, 1981, that Combustion Engineering Analysis CE-NPSD-154, " Natural Circulation Cooldown,"
demonstrated that such a cooldown can be achieved without drawing a bubble in the reactor vessel head.
Further, if a void was to occur during reactor coolant system depressurization, no structural damage would occur.
The licensee went on to say that a natural' circulation test program would be performed at Waterford 3 prior to commercial operations.
The licensee did conduct a natural circulation test program which, in part, took credit for testing performed on a similar reactor (San Onofre Unit 2). Review of the test program that was actually performed is contained in the Waterford 3 Safety Evaluation Report (SER)
and discussed in its various supplements.
In a letter dated February 29, 1984 the licensee submitted CEN-259, "An Evaluation of the Natural Cooldown Test Performed at the San Onofre Nuclear Generating Station," to confirm the applicability of that test to Waterford 3.
Ir: order to complete verification of the applicability of the San Onofre test the NRC requested additional information concerning Waterford 3 in a letter dated May 11, 1987. The licensee responded to the request with a submittal dated July 7, 1987.
The review of the test procedures used in the test conducted at Waterford 3 is documented in NRC Inspection Report 50-382/85-16 while review of the testing performed is contained in NRC Inspection Report 50-382/85-20.
Analysis of the acceptability of the Waterford 3 safety-grade emergency feedwater to support cooldowns is contained in the Waterford 3 Final Safety Analysis Report (FSAR). The review cf that analysis by the NRC is in the SER.
At the time of the licensee's response, to Generic Letter 81-21 Waterford 3 did not have in place procedures or training that covered reactor vessel voiding during natural circulation cooldnwn, but the licensee implemented such procedures and, training. The NRC inspector has reviewed approved procedures such as Emergency Operating Procedures OP-902-003, Revision 2, " Loss of Forced Flow Recovery Procedure," 0P-902-004, Revision 2, " Excess Steam Demand Recovery Procedure," 0P-902-005, Revision 2, " Degraded Electrical Distribution Recovery Procedure," and OP-902-006, Revision 2, " Loss of Main Feedwater
Recovery Procedure," and found they contain guidance for recognizing and dealing with reactor vessel voiding.
Further, the NRC inspector reviewed
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reactor operator training lesson plans in the areas of heat transfer / fluid flow and emergency operating procedures to verify voiding prevention and--
mitigation were discussed along with natural circulation cooldown.
Finally, the NRC inspector discussed, with a member of the licensee's
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training staff, the capabilities of the recently installed plant simulator. The inspector was. informed that the simulator, when fully j
operational, will have the' ability to simulate voiding during natural
circulation, and training will be conducted to cover that subject area.
No violations or deviations were identified.
11. Onsite Review Committee
The NRC inspector continued the review of the activities of the Plant
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Operations Review Committee (PORC) that was begun in NRC Inspection Report 50-382/87-01. During the current. inspection period, the NRC inspector reviewed meeting minutes for selected PORC meetings held between the beginning of June 1986 and the end of May 1987.
Except.for a few
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administrative errors which were discussed with licensee management, the j
NRC inspector found the meeting minutes acceptable.
On June 18, 1987, the NRC inspector attended the regularly scheduled weekly meeting of the PORC sd verified the requirements of Technical Specification 6.5.1 were met.
It was noted during the meeting that PORC
final reviews of Potentially Reportable Events (PRE) were significantly backlogged given the initiation dates of the PRE reviewed.. PORC approval of PRE packages is required by Procedure UNT-6-010, Revision 2, " Event Evaluation and Reporting." Approval of such packages by PORC, in some cases over two years after the event, is unacceptable. The NRC inspector
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discussed this problem with the plant manager who agreed the backlog had to be reduced. The plant manager went on to make the following points to the NRC inspector:
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The newly formed events analysis group, which was formed in response j
l to NRC and licensee recognition of reporting problems, identified the l
l problem and is working to reduce the backlog.
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Though the PRE packages have not gotten final approval, initial evaluations for deportability had been made upon initiation as i
required by the procedure, j
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In all.cses where unapproved PRE packages had resulted in LERs the LER was reviewed and approved by PORC.
This problem is identified as an unresolved item pending licensee dispositioning of the PRE backlog and final PORC verification of proper reporting of events.
(382/8714-01)
No violations or deviations were identified.
12.
Information Notices j
i In response to IE Information Notice 87-21, " Shutdown Order Issued 8ecause Licensed Operators Asleep While on Duty," the licensee has made the plant
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operations staff aware of this incident.
The licensee has initiated i
backshift plant tours conducted by management personnel.
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Exit Interview The inspection scope and fir. dings were summarized on July 15, 1987, with
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those persons indicated in paragraph 1 above.
The licensee acknowledged the NRC inspectors findings.
The licensee did not identify as proprietary.
any.of the material provided to or reviewed by the NRC inspectors during
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this inspection.
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