IR 05000397/1986007
| ML17278A641 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/25/1986 |
| From: | Ivey K, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17278A640 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-2.F.1, TASK-3.D.1.1, TASK-TM 50-397-86-07, 50-397-86-7, GL-85-06, GL-85-6, NUDOCS 8603180468 | |
| Download: ML17278A641 (12) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report No.
Docket No.
License No.
50-397/86-07 50-397 NPF-21 Licensee:
Washington Public Power Supply System P.
O. Box 968 Richland, Washington 99352 Facility Name:
Inspection at:
Inspection conducted:
Richland, Washington February 3-7, 1986 Inspector:
K. D.,Ivey, "Jr.","
eacto'r, Approved By:
T. Young, Jr.i,'h'; Eng'
ctor e
ng Section Date Signed y-~-N Date Signed Summary:
Ins ection durin the eriod of Februa 3-7 1986 (Re ort No. 50-397/86-07)
Areas Ins ected:
An unannounced, routine inspection by an NRC region based inspector for the follow-up of TMI Action Items and Generic I,etter 85-06.
The inspection involved 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> by one NRC inspector using module Nos.
30703, 25565, and 92703.
Results:
No violations or deviations were identified.
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DETAILS 1.
Persons Contacted 2.
J.
W. Baker, Assistant Plant Manager
>'<D. S. Feldman, Plant Quality Assurance Manager
-'R. Quay, Manager,, General and Technical Support Training
'R.
C. Mertens, QA Compliance Engineer D. Gano, Shift Technical Advisor'S.
Davison, Compliance Engineer
"J. Priyett, Non-Iicensed Operator Training Supervisor I
I The inspector also< held discussions with plant engineers during the inspection.
i
+Denotes those indiv'idual's attending the exit interview on February 7, 1986.
,In addition, Mr. R. Pate, Mr. P. Quails and Mr. R. Barr of the NRC were, present.,
I I R
TMI Action Items
'I
'D Item I.D.2 (Closed)'Safet Parameter Dis la S stem" iPosition:
NUREG-0737 requires the addition of a Safety Parameter Display System (SPDS) in the control room to display for operating personnel a minimum set of plant parameters which define the safety status of the'lant.
Additional guidance and clarification is given in NUREG-0696 and generic letter 82-33.
Findin s and Conclusion:
The SPDS function is performed by the SPDS console and select plant instrumentation suitably human engineered to satisfy the intent of the requirements.
This was previously reviewed (Inspection Report Nos. 50-397/84-08 and 85-06) with the only item necessary for completion being a Technical Specification submittal covering the SPDS.
The licensee also committed to address this submittal with NRR.
In amendment No. 36 to the WNP-2 FSAR, dated December 1985, the licensee stated its position that,
"a technical specification for the SPDS, a non-seismic, non-Class 1E, non-single failure proof system without seismically qualified backup, is not warranted especially when the instrumentation providing input. to the SPDS is already the subject of technical specifications".
Therefore, this item is closed.
No violations or deviations were identified.
B.
Item II.F.l Accident Monitorin The inspector verified the licensee's actions taken in response to the following NUREG-0737 sub-items are as documented in correspondence between the licensee and the NRC.
In the Safety Evaluation Report (SER) for WNP-2 (NUREG-0892 dated March 1982), the
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NRC concluded that the licensee's systems complied with the provisions of the TMI Action Plan.
Areas of inspection included:
Reviews to ensure that:
as-built drawings reflect the actual system designs; and procedures exist for operation and surveillance of the systems in accordance with the Technical Specifications; Visual verification of accessible portions of the systems; and Visual verification of the control room indicators.
Sub-item 4 (Closed)
Containment Pressure Monitor Position:
NUREG-0737 requires that a continuous indication of containment pressure be provided in the control room of each operating reactor.
Measurement and indication capability shall include three times the design pressure of the containment for concrete, four times the design pressure for steel, and -5 psig for all containments.
Findin s and Conclusion:
The licensee has installed three sets of redundant instrumentation.
These ranges (-5 to +3 psig,
to 25 psig, and 0-180 psig) cover the required range of three times containment design pressure to -5 psig.
Indication is continuous in the control room on panel No. 813-P601 and the Safety Parameter Display System (SPDS).
Surveillance procedure No. 7.4.3.7.5.6
"Primary Containment Pressure Monitoring" is required to be performed at least once every 18 months to satisfy the Technical Specifications.
The inspector concluded that the licensee has satisfied the requirements of NUREG-0737.,
This sub-item is closed.
No violations or deviations were identified.
(2)
Sub-item 5 (Closed)
Containment Water Level Monitor Position:
NUREG-0737 requires that a continuous indication of containment water level be provided in the control room for all plants.
For BWRs, a wide range,,instrument shall be provided and cover the range from the bottom to five feet above the normal water level of the suppression pool.
Findin s and Conclusion:
The licensee has two redundant Class 1E, wide range systems.
Each system consists of a high pressure transducer located at the bottom of the suppression pool and a low pressure transducer located just below the diaphragm floor between, the, d'rywell and wetwell.
A third non-Class 1E channel is 'provided for backup.
These systems have a range of 0-65 feet above the lowest ECCS suction 'level.
The licensee also',has narrow range water level indication measuring
+25 feet from 'normal water level in the pool.
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Continuous indication for both narrow range and wide range suppression pool water level is located on panel H13-601 in the control room.
Surveillance tests No. 7.4.3.7.5.3
"Suppression Pool Narrow Range Level and Suppression Chamber Pressure Monitoring" and No. 7.4.3.7.5.31
"Suppression Pool Wide Range Level Monitoring" are performed at least once every 18 months to satisfy Technical Specification requirements.
The inspector concluded that the licensee has satisfied the requirements of NUREG-0737.
This sub-item is closed.
No violations or deviations were identified.
(3)
Sub-item 6 (Closed)
Containment H dro en Monitor Position:
NUREG-0737 requires that a continuous indication of hydrogen concentration in the containment atmosphere be provided in the control room.
Measurement capability shall be provided over the range of 0 to 10 percent hydrogen concentration under both positive and negative ambient pressure.
Findin s and Conclusion:
The licensee has installed redundant hydrogen monitoring systems with a range of 0-30 percent hydrogen concentration.
Atmosphere samples from three locations inside the primary containment and one location in the suppression chamber are sequentially monitored by each of t'e two redundant analyzing systems.
Continuous indication is provided in the control room on Panel H13-P827 Board Kl and Panel H13-P811 Board K2.
Surveillance procedure No. 7.4.3.7.5.9
",Accident Monitoring Instruments Drywell Hydrogen Concentration" is required to be performed every three months to satisfy Technical Specification requirements.
'T The inspector noted, however, that the, hydrogen monitors were not environmentally qualified.
The replacement of these systems with qualified inst'rumentation'was made a license condition to be completed prior to startup following the first refueling o'utage.
The'~ ins'pector ~therefore concluded that this NUREG-0737 item is satisfied and the environmental qualification of,the system will,be followed in accordance with the license condition.
This;sub-item is closed; No violations or deviations were identified.
Item III.D.l.l (Closed)
"Primar Coolant Sources Outside Containment" Position:
NUREG-0737 requires that licensees develop a program to review systems for potential radioactive leakage paths, implement a program to reduce leakage through, increased surveillance, and record actual measured leakage rates and report them to the NRC.
Findin s and Conclusion:
As documented in Inspection Report 50-397/84-11, the NRC reviewed the licensee's actions on this item
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' ')<<), ',,', ",'>>.y ">>y) (p 1 "'f)'f., > I > 4 V\\ ~ I >h ~ ) ~ r ff '). h ."., I .)>ALII 3s'.f ' f '<<h)4 kp<<y, > I 'pf,.'. Ill>>l hf'0 ff<<3 (>> 113 ~)I 'I I Flp 'l' v,l ) ) v>>4> 1 llv 3 ~ I 'I'3 4"','; X p ,y>fp, . I .'h 3'p, <<A 3 f ." >1') f '4 <<y a) 'JIf"'3IF> I f(> 'g,", J I) $ and concluded that a program for'dentifying leakage paths and reducing these paths through increased surveillance had been implemented. The only remaining item for review was the record of actual measured leakage rates for review by the NRC to be followed up after initial starts of the plant. The program is outlined in Administrative Procedure 1.5.6 "Leakage Surveillance and Prevention Program" and provides for a "Leakage Coordinator" who has responsibility for the various aspects of the program. The program includes a quantitative leakage check for leakage paths once per refueling cycle (18 months), special provisions for maintenance work requests dealing with leakage related problems, and a status sheet for equipment exhibiting leakage. Procedure 8.3.2 "Leakage Surveillance and Prevention" provides for implementation of the program. The inspector reviewed the completed results from the program for the last three years (3 sets of data) and the "Leakage MWR" list and concluded that the program is being implemented per the procedures. The licensee,'s'ctions 'appear to satisfy this NUREG-0737 requirement ~>.,and therefore,,'this item is closed. i No violations'r deviations were identified. 3. Generic Letter ~85-06 (Closed) '" A Guidance for ATWS E ui ment that is , not,Safet -.Related". i On June, 1, 1984, the NRC approved" publication of a final rule, CFR 50.62, regarding the reduction. of risk from anticipated transients without scram (ATWS) 'events~ for light-water cooled nuclear plants. This generic letter,was issued to;provide explicit gA guidance for non-safety related equipment encompassed, by the ATWS rule. Section 50.62(d) requi'red that each licensee develop and submit a proposed schedule for , meeti'ng the requirements of the rule within 180 days after issuance of the QA guidance (issued April '16, 1985). The rule also required justification if the schedule called for final implementation later than the second refueling outage. after July 26, 1984. The licensee responded to this item by letter on October 14, 1985 (7IG02-85-718, G. C. Sorensen to W. R. Butler). The licensee stated that, "the Supply System 'intends to complete implementation of the ATWS modifications by the end of the planned Spring 1988 refueling/maintenance outage". Since this will be the third refueling outage after July 26' 1984, the licensee requested NRC concurrence on the schedule. There was no response as of the date of this report and the licensee stated that. they would initiate correspondence with NRR on the acceptance of this schedule. This item is closed. No violations or deviations were identifie ~ ~ ~ ~ << ~ ~ On February 7, 1986, an exit meeting was held with the licensee representatives identified in paragraph 1. The inspector summarized the scope of the inspection and findings as outlined in this report. tl h P a ~ o ~ t) II )f , l l< Jr LC Ci 'f t