IR 05000255/1987003
| ML20212N486 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/09/1987 |
| From: | Danielson D, Yin I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20212N468 | List: |
| References | |
| 50-255-87-03, 50-255-87-3, NUDOCS 8703130044 | |
| Download: ML20212N486 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-255/87003(DRS)
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Docket No. 50-255 License No. DPR-20 Licensee:
Consumers Power Company 212 West Michigan Avenue-Jackson, MI 49201
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Facility Name:
Palisades Nuclear Generating Plant
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Inspection At:
Palisades Site, Covert, Michigan Inspection Conducted:
January 21-22, February 17-19, and March 3,1987 2l7/f7
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Inspector:
I. T. Yin Date 3!6!I7 Approved By:
D. H. Danielson, Chief Materials and Processes Section Date Inspection Summary Inspection on January 21-22, February 17-19, and March 3, 1987 (Report No. 50-Zbb/8/003(URS))
Areas Inspected:
Routine announced inspection of the testing, and seal replacement program for the large bore steam generator snubbers (SGSs).
(30703B,92701B,70370B)
Results:
No violations or deviations were identified.
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8703130044 070309 PDR ADOCK 05000255 o
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DETAILS 1.
Persons Contacted Consumers Power Company (CP)
- J. G. Lewis, Technical Director
- K. E. Osborne, Projects Superintendent
- R. D. Orosz, Engineering and Maintenance Manager
+*B. V. Van Wagner, Inservice Inspection (ISI) Supervisor
+*D. J. Malone, Licensing Analyst
- C. S. Kozup, Technical Engineer
+*T. D. Rexius, ISI Senior Technician W. J. Axdorff, General Engineer R. Ward, Senior Technical Analyst U.S. Nuclear Regulatory Commission, Region III
+*E. R. Swanson, Senior Resident Inspector
- Denotes those attending the management exit meeting on February 19, 1987.
+* Denotes those attending the followup telephone conference on March 3, 1987.
2.
Licensee Action on Previous Inspection Findings (Closed)OpenItem(255/83025-01):
Licensee will conduct SGS functional tests to ensure operability.
This item is closed.
See Paragraphs 3 through 5 for details.
3.
ReviewofPlantTechnicalSpecifications(TS)
The NRC inspector reviewed the Palisades TS Section 3.20, " Shock Suppressors (Snubbers)," and Section 4.16 " Inservice Inspection Program for Shock Suppressors (Snubbers),'g Amendment No. 69, March 12, 1982, and determined that it was in compliance with the NRC generic letters listed below.
The functional test exemption for the large bore snubbers with load capacity of 50 kips and above had been removed.
NRC-NRR Director, Division of Licensing letter to all power reactor
Licensees (exceptSEPLicensees),"TechnicalSpecificationRevisions for Snubbers Surveillance," November 20, 1980.
NRC-NRR Director, Division of Licensing letter to all SEP licensees,
samesubject, March 23, 1981.
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In a CP letter to Region III, " Inspection Report No. 83-25 Open Item Response," May 29, 1985, the licensee stated:
"For the 1985/1986 Palisades Refueling Outage, and for each subsequentrefuelingoutage,foursteamgeneratorsnubbers(25%)
will be functionally tested.
This schedule will provide both-functional assurance and the necessary inspection interval to meet the ~eight year service life criteria recommended by the Palisades Plant Mechanical Maintenance Staff.
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In the event of one steam generator snubber failure out of the four tested, no additional steam generator snubbers will be tested provided the problem is non generic..For each additional snubber failure; however, two additional snubbers will be tested until no steam generator snubber failures are found or all snubbers have been tested. Generic failures will be appropriately handled as the specific circumstances require."
These provisions are not presently included in the TS.
However, CP stated that the SGS testing requirements will be included in the next TS amendment.
The NRC inspector reviewed the CP draft TS change request for Sections 3.20 and 4.16, and had no adverse comments.
This matter is considered resolved.
'4.
Review of SGS Testing Program a.
Review of Control Procedures The NRC inspector reviewed the following procedures relative to the SGS testing:
Palisades Nuclear Plant (PNP) Engineering Manual Procedure,
No. EM-09-07, " Testing of Plant Snubbers," Revision 0, November 25, 1986.
PNP Technical Specifications Surveillance Procedure, No. RM-45,
" Functional Testing of Seismic Hydraulic Restraints,"
Revision 10, July 22, 1986.
RM-45 includes the following SGS test acceptance criteria:
6.2 ITT Grinnell 8" Bore x 5" Stroke Hydraulic Snubbers.
6.2.1 1 to 6 in/ min for lockup velocity in both tension and compression.
6.2.2 0.004 in/ min to 2 in/ min for bleed rate in both tension and compression.
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f, The NRC. inspector inquired about the basis for the 0.004 in/ min criterion.
After further review, taking into consideration the
.short term transient thermal movements included in. Internal.
Correspondence, BW87*002, February 13, 1987, the responsible.CP engineer decided the criterion should be changed to 0.0008 in/ min.
The NRC inspector reviewed the draft revision of RM-45, February 19, 1987, to incorporate the above new acceptance criterion, and had no adverse comments.
b.
Review of SGS Test Procedure The-NRC insp'ector reviewed Wyle Laboratories Test Procedure -
No. 46941, Hydraulic Snubber Test Procedure for Consumers Power Company Palisades Generating Plant," Revision B, September 8,1983, and made the following comments:
Forverylowsnubbertestvelocities,suchas0.010in/ min,a
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dial indicator and stop watch were used. This measurement should be qualified and prescribed in the procedure.
The procedure should be more specific regarding the
documentation of snubber leakage under load during testing.
Leak initiation, load, and severity of leakage (excluding surface wetness and minute seepage) should be documented for engineering followup and evaluation.
The licensee is reviewing this matter.
This is an Unresolved Item.
(No.255/87003-01)
c.
Review of Past SGS Test Records All 16 SGSs were refurbished and functionally tested during the last refueling outage.
The NRC inspector reviewed the following Wyle test reports and had no adverse comments:
Wyle Report No.
Snubber No.
Issuance Date 46941-1885
2/7/84 46941-1672
2/7/84 46941-1880
11/10/83 46941-1890
1110/83 46941-1888
11 10/83 46941-1887
11 10/83 46941-1670
11/10/83 46941-1878
11/10/83 46941-1886
11/10/83 46941-1889
11/10/83 46941-1883
11/10/83 46941-1881
11/10/83 46941-1884
11/10/83 46941-1891
11/10/83 16941-1882
2/7/84 46941-1879
11/10/83
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b-d.
Review of Present SGS Tests Records The NRC inspector reviewed the following as-found SGS tests conducted during the present refueling cutage and had no adverse conn:ents:
Wyle Rer: ort No.
Snubber No.
Issuance Dat_e_
48059-2
1/14/86 48059-3
1/14/86 48059-4
1/14/86 48059-5
1/14/86 e.
Review of SGS Sited Staff Visual Inspection Records t
The NRC inspector reviewed the records of visual inspections and noted that the SGS leakage problem had been identified during the site staff routine surveillance of the SGSs. The licensee reinspection / corrective actions are discussed in Paragraph 4.f below. The records reviewed included:
Date of CP Reservoir A Reservoir 0 CP Records Level Filled Level Filled Actions 7/15/80 3/4 3/4 None 10/23/81 Less than 1/2 Between 1/2 Filled to 3/4 Reservoir A 8/23/83 Empty Empty Note 1 4/11/04 3/4 3/4 None 6/15/84 5/8 5/8 None 10/01/84 1/2 1/2 None 8/24/85 Near Empty Near Empty Note 2 12/13/85 7/16 7/16 None Note 3 3/10/86
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4/10/86 3/4 3/4 None 7/15/86 1/2 1/2 Note 4 Notes:
1.
CPEventReport(ER)No.E-PAL-83-176wasissuedonAugust22, 1983. All 16 SGSs were forwarded to Wyle for refurbishment and testing.
In addition to the SGS fluid leak problen, fluid of unknown type was found in the SGSs, and all SGSs failed to lockup due to improper manufacturing of the control valve blocks.
2.
Reservoir A measured 1/4" and Reservoir B measured 1" of fluid was left in the botton. ER No. E-PAL-85-071 was issued on August 20, 1985. Corrective action included tightening the tubing fittings and evaluation of leak rate.
3.
Seal weld made on SGS No. 47 to stop fluid leakage.
4.
Filled fluid back into Reservoirs A and B to 3/4 level.
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f.
Observation of SGS System Conditions On February 18,1987, the NRC inspector inspected all 16 SGSs at steam. generators A and B.
Fluid levels in Reservoirs A and B were within acceptable levels. Seepage at several tubing fittings and SGS seals were observed; however, the leekage was not considered to be excessive. A puddle of liquid was found below SGS No. 54, and the bottom of the SGS was wet; however, na dripping was observed.
Several SGS control valve block installation positions appeared to be questionable. The CP staff comitted to followup on the NRC inspector's findings, and issued Work Request No. 084429 on February 19, 1987, for the inspection and repair of the deficiencies if required. CP management stated that Region III would be inforned of any nonccnformances identified during this inspection. They also agreed to inform Region III of any problems that ray be identified during the September 1987 maintenance plant outage SGS inspection.
ThisisanUnresolvedItem.(No. 255/87003-02)
5.
Personnel Interviews During his review of past SGS test and visual inspection records, the NRC inspector questioned the qualification and the adequacy of training provided for the CP staff assigncd to the task. Personnel qualification has improved; however, additional technical and on-the-job training for the newly assigned staff was recenrended by the NRC inspector.
6.
Unresolved Item An unresolved item is a matter about which more information is required in order to ascertain whether it is an acceptable item, an open item, a deviation, cr a violation. Two unresolved items, disclosed during this inspection are discussed in Paragraphs 4.b. and 4.f.
7.
Exit Interview The NRC inspector ret with licensee representative (denoted in Paragraph 1) at the conclusion of the inspection. The inspector sumarized the scope and findinss cf the inspection. The inspector also discussed the likely informational content of the inspection report with regard to documents reviend by the inspector during the inspection. The licensee representatives did not identify any such documents as proprietary.
A followup on findings identified during this inspection was conducted through a telephone conference on March 3,1987. The CP steff indicated that they had ccmpleted the action delineated in Paragraph 4.f.
Two tubing connections were tightened. The puddle of liquid beneath SGS No. 54 appeared to be SGS fluid. The area was c1 caned so any SGS leakage could be easily identified during the September 1987 plant cutage. Thrce control valve block vent positicns were found nct to be installed in the optin:um position; however, they were evaluated to be acceptable. The NRC inspector stated that Region III will followup on the licensee's actions during a subsequent inspection.
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