IR 05000255/1987003

Insp Rept 50-255/87-03 on 870121-22,0217-19 & 0303.No Violation or Deviation Noted.Major Areas Inspected:Testing & Seal Replacement Program for Large Bore Steam Generator Snubbers

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: IR 05000255/1987003 ML20212N467
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 Inspection At: Palisades Site, Covert, Michigan Inspection Conducted: January 21-22, February 17-19, and March 3,1987

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Inspector: I. T. Yin 2l7/f7

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Date Approved By: D. H. Danielson, Chief 3!6!I7 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 identifie PDR ADOCK 05000255 o PDR

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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, 198 +* Denotes those attending the followup telephone conference on March 3, 198 . Licensee Action on Previous Inspection Findings (Closed)OpenItem(255/83025-01): Licensee will conduct SGS functional tests to ensure operabilit This item is close See Paragraphs 3 through 5 for detail . 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 belo The functional test exemption for the large bore snubbers with load capacity of 50 kips and above had been remove * NRC-NRR Director, Division of Licensing letter to all power reactor Licensees (exceptSEPLicensees),"TechnicalSpecificationRevisions for Snubbers Surveillance," November 20, 198 * NRC-NRR Director, Division of Licensing letter to all SEP licensees, samesubject, March 23, 198 ..

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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 teste 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 Staf ,

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 amendmen 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 resolve '4. Review of SGS Testing Program 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, 198 * PNP Technical Specifications Surveillance Procedure, No. RM-45,

" Functional Testing of Seismic Hydraulic Restraints,"

Revision 10, July 22, 198 RM-45 includes the following SGS test acceptance criteria: ITT Grinnell 8" Bore x 5" Stroke Hydraulic Snubber . to 6 in/ min for lockup velocity in both tension and compressio . .004 in/ min to 2 in/ min for bleed rate in both tension and compressio .

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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. Interna Correspondence, BW87*002, February 13, 1987, the responsible.CP engineer decided the criterion should be changed to 0.0008 in/ mi The NRC inspector reviewed the draft revision of RM-45, February 19, 1987, to incorporate the above new acceptance criterion, and had no adverse comment 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 dial indicator and stop watch were used. This measurement should be qualified and prescribed in the procedur * The procedure should be more specific regarding the documentation of snubber leakage under load during testin Leak initiation, load, and severity of leakage (excluding surface wetness and minute seepage) should be documented for engineering followup and evaluatio The licensee is reviewing this matte This is an Unresolved Ite (No.255/87003-01) 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 N Snubber N Issuance Date 46941-1885 46 2/7/84 46941-1672 47 2/7/84 46941-1880 48 11/10/83 46941-1890 49 1110/83 46941-1888 50 11 10/83 46941-1887 51 11 10/83 46941-1670 52 11/10/83 46941-1878 53 11/10/83 46941-1886 54 11/10/83 46941-1889 55 11/10/83 46941-1883 56 11/10/83 46941-1881 57 11/10/83 46941-1884 58 11/10/83 46941-1891 59 11/10/83 16941-1882 60 2/7/84 46941-1879 61 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 N Snubber N Issuance Dat_e_

48059-2 47 1/14/86 48059-3 51 1/14/86 48059-4 55 1/14/86 48059-5 59 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 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 3/10/86 --- --- Note 3 4/10/86 3/4 3/4 None 7/15/86 1/2 1/2 Note 4 Notes: 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 block . 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 rat . Seal weld made on SGS No. 47 to stop fluid leakag . Filled fluid back into Reservoirs A and B to 3/4 leve <

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.. 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 observe 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 inspectio 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 inspecto . 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 . 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 proprietar 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 inspectio _.