ML20235W027

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Advises of 861117 Telcon W/M Evans Indicating That Inboard Valve Installed After Fuel Loading Was Finished & Failed Local Leak Rate Test.Indications Existed That Tungsten Carbide Coating Smeared.Addl Details Will Be Provided
ML20235W027
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 11/17/1986
From: Florek D
NRC
To: Bettenhausen L
NRC
Shared Package
ML20235W026 List:
References
FOIA-87-438 NUDOCS 8710150548
Download: ML20235W027 (25)


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FMPORT Laborat ory No. 876757 oaot a No PCH-1762 Client No. NMP2-FPO-27671 cave September 19, 1986 Client : Stone and Webster Engineering Corporation Agents for Niagra Mohawk Power Corporation i Nine Mile Point Nuclear Station - Unit 2 Lycoming, NY 13093 Sample

Description:

Four (4) Samples of Reference Materials Four (4) Paste-like Samples - Unknown ,

Six (6) Fine Solid Samples - Unknown Subtitted By: Client  !

Subciitted To: PTL-Inspectorate Inc., Chemical Department ,

Service Requested: Comparison Reference Samples verses Paste-like Unknowns Examination, Identi ficat ion of Unknowns Method of Test: Inf rared Spect rophot omet ry Energy Dispersive X-ray Analysis ,

Scanning Electron Microscopy '

X-ray Di f fract ion Direct Current Plasma Emission Spectroscopy  !

l 4

Reported To: Stone and Webster Engineering Corporation i Attn: John Montaro and Greg Rodgers l

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l The above identified reference and unknown materials were submitted to this i laboratory for examination or. September 9, 1986. I l

Specific identifications of the materials were as follows:

Reference Materials- 1 Neolube, Hyprez Compound, Molykote 505 and Lapping Compound, Blue 15 LMA i I

Unknown Paste-like Mat erials l Spool Seat 6B, Thurst Washer 6B, Molykote? 6B and Northwall Valve, Body, and Base Unknown Fine Solids:

Ball ID 6B, Inboard below Spool, Bore 6B, Outboard below Spool, N. Body Wall and Ball OD6B Page I of 5

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St one ,'end 'Webst er Enginee ring Corporat ion Order No. PCH-1762 September '19, 1986- Laboratory No. C76757 I

Examinat ion of the he ference Mat erials was conduct ed by Infrared Spect ro-phot omet ry for ident i ficat ion of major component s. The purpose was to then, upon examinat ion of other samples by the same t echnique, to determine if similar component s and associated compounds were present in the unknown materials.

The " Unknown Past e-like Mat erials" and " Ball ID 6B" Samples, upon examiantio1, result ed in the following:

Re fe renc e / Sample , fraction Composition

1. Reference Materials
1) Molycot e 505, as received inorganic silicates and a hydrocarbon component
2) Molycote 505, chloroform Pet roleum hydrocarbon similar solubles to a type of petrolatum
2) Lapping Compound Blue 15 Ethylene oxide condensation LMA, as received product (major component)

Lapping Compound Blue 15 Ethylene oxide condensation LMA, chloroform solubles product

3) Hyprez Diamond Compound, Ethylene oxide condensation as received product.(predominant component)

Hyprez Diamond Compound, Ethylene oxide condensation chloroform solubles product

. 4) Neolube, as received Scattering of infrared beam suggests presence of graphitic carbon. Solvent was identified as isopropanol 1

Noelube, chloroform Scattering of infrared beam solubles suggests presence o.f graphitic carbon (fine carbon particles  ;

passed through filter paper) l II. Sample Identification 6B Molycote? , as Similar to Mo3ycote Reference, received as received 6B Molycote?, chloroform Similar to Molycote Reference, solubles chloroform solubles 6B Thrust Washer, as Scattering of infrared beam received suggests presence of graphitic carbon 6B Thurst Washer, Trace amount of unidentifiable chloroform solubles material recovered possibly an ester Page 2 of 5

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St one;and :Vebst er Engineering ~ Corporat ion PCH-1762 Laboratory No. 676757 September 19. 1986: r:

Re fe rence/ Sample , ' f ract ion Compos it ion ,

II. - Sample Ident i ficat ion (con't .)

6B Spool Seat, as Similar to Molycote Reference, received. as= received 6B-3 . Spool Seat ' chloroform Similar- to Holycote Re ference, solubles chloroform solubles .

NorthlWall Valve' Body and Seatter'ing of in't ared beam Base, .4 received suggests presence of graphitic carbon North Wall Valve Body and Observed hydrocarbon and ester -

Base, chloroform solubles absorptions 6B Ball Rust'ID Observed hydrocarbon, amine chloroform solubles ester and ether linkage-absorptions possibly including an alkyl substituted amine-and/or amide examination of samples was also conducted by Energy Dispersive X-ray Analysis.

This' technique detects the elemental const ituents: of samples on a semi-quantitative basis. Fourteen ( 14) su:h examinations were cenducted and the findings are presented as Attachment I.

. The inorganic- (chloroform insoluble fraction) portion of ' the Re ferences were examined in addition to the unknown materials.

Four (4) samples were examined under electron microscope for particle size.

The original photographs were returned by Client's representative. The.following summary of the samples and findings is provided.

Sample Part icle Size !-Phot ographed North Body Wall 14 I um Outboard below Spool 263 um Inboard below Spool 158 um Ball OD 238 um Page 3 of 5

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.,. ,c St onef.and Webst er Engineering ' Corporation Order No. PCH-l?62

.Septimber 19, 1986 . Laborat ory No. 876757 The " Unknown fine Solids" were found to be composed predominantly of Iron (Fe).

Tlius, one sample was selected for. examination by X-ray Diffraction. The sample chosen'was " North' Body. Wall".. The out put from this examinat ion was returned with'

. client 's represent at ive. The major findinEs were as follows:

Major Component Te34 0 Magnetite >70 2 Minor Component 'Fe 0 Hematite I-10 %

73 The 'following informat ion on these' two compounds was taken from The Condensed Dictionary 10th Edit ion Van Nost rand Reinhold Company.

Magnetite: (Lodest one, Iron Ore, Magnet ic) of t en with Titaniue or Magnesium J- 72.4 % Iron content Hardness 5.5 to 6.5 (Mho's scale)

Hemat it e: (Red Iron Ore Bloodst one)

Hardness (Mho's scale) 6 Quantitative Chemical Analysis conducted on the North Body Wall by Direct Current P1&sma Emission Spectroscopy was conducted to confirm and quantify major.

components and to identify and quant i fy minor ' component s. Halides (Chloride and Fluoride) were evaluated on a water leach of the sample and a-loss by ignition was conducted as well.

The findings were as follows:

Major Iron (Te) 63 % (64.17 % by wet chemistry)

Carbon 1.60 %

Loss on Ignition 1000* 3.8 %

Minor Silicon 0.49 % Chromium 0.17 %

Manganese 0.59 % Zinc 0.13 %

Nickel 0.19 %

Trace Phosphorus 0.019 % Barium 0.01 %

Molybdenum 0.060 2 Cadmium 0.02 %

Titanium 0.043 % Tin 0.04 %

Cobalt 0.075 % Lead 0.04 %

Copper 0.080 % vanadium 0.002 %

Water extractable Fluoride 60 mg/g Chloride 98 mg/g 1 +

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  • Orddr No. ,PCH-1762-er' St one. And Webst er ' Engineering Corporat' ion - d' Sept ember.' 19, 1986- Limb'oratoryNo.. 876757 v c e

l Client inquiry concerning Tungsten cont ent : resu'It ed' in quantit'at ive ' analysis l of three samples - for.Tungst en as well as Iron, ' Si1 icon, and \ (=

Manganese.

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1 Inboard Outboard North Wall- i Below spool Below sp'ool ' Body

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Tungsten. 'O.075 % 0.045 %

0.050 %

Iron 60.8 % 60.4 % ' 62.8 %  !

< Silicon 0.28 %~ Oi20 % 0.24 %

+ Manganese 0.46 % .;0.42 % .; .

0.58 %

All of the information provided. above was submitted to client via.telefax

-over the period of September 9 - September 10, 1986.  :,

3 Components present in the;" Unknown Past'e-like Materials" examined by Infrared Spect rophometry, we found to be similar to and probably originating from the

" Reference Materials".

l A possible source of the " unknown Fine Solids" was' n.ot found'among the " Reference Materials". However, these samples exhibit commonality 'In their high content of iron (oxides). 'D I.

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1/5 NMP2 MEETING IN BETHESDA I OPTIONS

1. REPAIR BALL VALVES - PREFERRED BY LICENSEE AND NRC STAFF PRESENT (Vollmer, Bernero, Lanais et. al.) EXCEPT PM REPAIR ONLY THE ONE BALL AND JUSTIFY THE USE OF THE OTHERS WHICH

} SHOWED SOME EVIDENCE OF DEGRADATION BY SOME COMBINATION OF ANALYSIS AND TESTING FOR N STROKES WHERE N GREATER THAN THE NUMBER EXPECTED l DURING FIST CYCLE. APPROACH IS TO JUSTIFY WORST CASE DEGRADATION TAKING INTO ACCOUNT MITIGATING FACTORS NOT CONSIDERED IN SAFETY ANALYSIS PER GENERIC LETTER 86-17 AND NUREG II69,MSIV LEAKAGE AND LCS FAILURES.

1 MAJOR REMAINING TECHNICAL ISSUE IS MIXING DIVISIONS WITHIN RPS CHANNELS TO PREVENT INADV8RTANT CLOSURES AND PERMIT TESTING. SERIES SOLENDID OPTION TO CORRECT THIS WOULD TAKE ONE MONTH. PREFERRED APPROACH BY NRC STAFF PER 1/16 MEETING AND SER WILL BE ISSUE)

INDICATING CURRENT TRANSFER CIRCUIT UNACCEPTABLE.

NO LICENSE OR TS CHANGES EXPECTED WITH THIS OPTION.

WILL MEET TS WHILE PERFORMING MODIFICATIONS.

PROTOTYPE PROGRAM WILL REMAIN AS SPECIFIED IN LICENSE.

ALARA ISSUE SHOULD BE ADDRESSED IF INTENT IS TO OPERATE FOR ONLY ONE CYCLE WITH BALL VALVES.

2. REPLACE BALL VALVES WITH Y PATTERN GLOBE VALVES LICENSEE HAS VALVES AVAILABLE AND HAS COMPLETED DESIGN. CONSULTANTS CURRENTLY REVIEWING IT. MODIFICATION WOULD TAKE 3-4 MONTHS.

LICENSE AND TS CHANGES WOULD BE REQUIRED. NO SIGNIFICANT HAZARDS.

CONCLUSION WOULD HAVE TO BE JUSTIFIED. PROBABLE BUT NOT ASSURED.

NRC STAFF CONCERNED ABOUT UNCERTAINTIES AND POTENTIAL PROBLEMS I ASSOCIATED WITH JUMPING INTO MODIFICATIONS OF THIS MAGNITUDE WITHOUT l ADEQUATE TIME TO PLAN AND REVIEW IT BEFOREHAND. l PROBABLY CAN JUSTIFY NOT INSTALLING LEAKAGE CONTROL SYSTEM (h0 WEVER, IT IS INCLUDED IN DESIGN PACKAGE).

3. STRIP 0FF C0ATING ON BALLS - DEMONSTRATED NOT FEASIBLE BY TESTING OVER WEEKEND.
4. REC 0AT ALL BALLS AGAIN - NOT DESIRABLE AND NOT SERIOUSLY DISCUSSED.

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PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I FEBRUARY 10, 1987 TO: James Blaha, Director, Program Support and Analysis Staff FROM: Thomas E. Murley, Regional Administrator, Region I Licensee / Facility Notification / Subject Beaver Valley Unit 2 2/10 SRI Fax DN 50-412 Structural Integrity Test Event At approximately 3:30 a.m., the licensee began pressurizing the containment for the Structual Integrity Test (SIT). As of 8:00 a.m., the containment was at 13 psig and the licensee was conducting outside wall surface examinations and documenting identified indications. The licensee plans to continue raising containn.cnt pressure in stages to a maximum of 52 psig. The estimated test completion date is 2/12. The licensee plans to conduct the Integrated Leak Rate Test shortly after SIT completion. Resident and specialist inspectors are following the licensee's testing activities.

Licensee / Facility Notification /Sybject Nine Mile Point 2 2/10 Resident PC DN 50-410 MSIV Update Event On 2/8 during a newly developed surveillance test, the Main Steam Isolation Valves (MSIVs) did not perform as expected. The test procedure attempted to measure the closure times of the 8 MSIVs with only one solenoid dump valve in the hydraulic control system being deenergized (two solenoid valves are installed on each MSIV). Two MSIVs did not close, five MSIVs did not meet the 5 second maximum closure time limit, and one MSIV met the 3 to 5 second limit but appeared to have both solenoids deenergized. NMPC is reevaluating the test procedure, verifying the installed circuits visually and electrically, and reviewing the logic design.

A prototype MSIV recently completed the first phase of hot testing at the manufacturer (Crosby). The valve had been cycled through approximately one half of expected usage in one plant operating cycle at operating temperature and pressure. Leakage testing was performed when the valve was just below 200 degrees F, and results were approximately 50 SCFH (acceptance criteria is 6 SCFH). At ambient temperature gross leakage occurred, and the valve could not be pressurized. Based on disassembly and examination, the packing between the seat ring and the piping is suspected to be the leakage path. The ball and seats showed no signs of previous failure modes but had some wear marks. The seating surfaces were bubble tested, and only minor leakage was observed.

However, the seat to piping packing was observed to be loose. It appeared that the packing remained compressed following the thermal cycles and was no longer resilient. The valve was packed with the Lattytex packing used in six i of the eight installed valves. The valve is being reassembled and will be retested to verify the failure mechanisms.

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REGION I MORNING REPORT PAGE 2 FEBRUARY 24, 1987

' Licensee / Facility Notification /Subiect j

! Nine Mile Point 2 2/24 Resident PC ,

DN 50-410 MSIV Update l Event MSIV UPDATE As reported on 2/10, MSIVs 6A and 6B failed to close during a containment  !

isolation surveillance test, which attempted to close each MSIV using one of the two solenoid valves installed on each MSIV. The licensee disassembled the scienoid valves on the four inside containment MSIVs and found that a spacer in the valve spring assembly was missing from six of fg {k )

the solenoids (both solenoids on MSIVs 6A, 6B, and 6C). These spacers had been added by a' design modification to increase the spring force in the valve. Documentation reviews and the successful testing of the outside containment MSIVs indicate all the spacers are installed in these valves. j Licensee / Facility Notification / Subject Nine Mile Point 2 2/22 ENS, 2/24 R1 PC DN 50-410 Missed Fire Watch Event On 2/22 at 4:00 a.m., the licensee on-shift fire chief discovered that two hourly fire watch patrols had been missed. The missed patrols were at i 12:34 a.m. and 1:34 a.m. for an inoperable fire detection zone in the North Auxiliary Bay. The fire detection zone was returned to service at 2:35 a.m..

The apparent cause of the missed patrols was miscommunication between the fire watch and his supervisor.

Licensee / Facility Notification / Subject Nine Mile Point 2 2/24 ENS, 2/24 RI PC DN 50-410 Inadvertent ESF Actuation Event.

At 12:41 a.m. on 2/24, an automatic Engineered Safety Feature actuation occurred as a result of personnel error. While performing Main Steam Line Isolation g

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response time testing, an operator misunderstood directions given him and mistakenly opened the supply breaker to the containment isolation logic circuit.

This caused a containment isolation, reactor water cleanup system isolation, shutdown cooling isolation, reactor building ventilation isolation, and automatic start of both trains of the Standby Gas Treatment System. All systems responded as designed.

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