IR 05000352/1981012

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IE Insp Repts 50-352/81-12 & 50-353/81-10 on 810801-30. Noncompliance Noted:During 810413-0814,daily Temp Readings Were Not Taken on Unit 1 Reactor Pressure Vessel
ML20031B992
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 09/09/1981
From: Durr J, Mccabe E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20031B984 List:
References
50-352-81-12, 50-353-81-10, NUDOCS 8110060409
Download: ML20031B992 (10)


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U.S. NUCLEM REGULATORY COMMISSIM 0FFICE OF IfGPECTION AND ENFORCEMENT

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50-352/81-12 Report No. 50-353/ri_in 50-352f.

Dociet No.

50-353 CPPR-106

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License No.

CPPR-107 Priority

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Category A

Licensee:

Philadelphia Electric Comoany 2301 Market Street Philadelphia, Pannsv1vania 19101 Facility Name: Limerick Generttino Station, Unit Nos. I and 2 Inspection at: Limerick, Pennsylvania Inspection cond eted: August 1 30,.1981 Inspectors:

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p. Pp DYr, Senior Resident Inspector

/ da'te s'igned date signed date signed Approved by: - 8ObM h 9b t.

L. nctace, Lnrer, Heactor date signed Projects Section 2B Inspecj.ionSummar$: (Unit No. 1)

Inspection on Auqust 1-30, 1981 (Report 50-352/81-12)

Areas intrected: A routine, unannounced inspection by the Resident Inspector of

'illectrical sabTe pulling, welding, licensee action on previous inspection findings, ard plant tours. The inspection involved 43 inspector-hours on site.

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Rtwlts; One item of noncompliance was ' identified in the four areas inspected

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(Failure to properly -tore the reactor pressure vessel, para. 3).

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1 Unit ' o. 2)' Inspection on August 1-30, 1981 (Report 50-353/81-10)

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. Areas Inspected: A routine, unannounced inspection by the resident inspector of

,Bcensce's action on previous inspection findings and plant tours. The inspection

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Results: No items of noncompliance were identified in the two areas inspected.

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' Region 1 Form 12 (Rev. April 77)

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- 8110060409 810911 PDR ADOCK 05000352

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DETAILS 1.

Persons Contacted Philadelphia Electric Company

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J.M..Corcbran,FieldQABranchHead F., J. Coyle Quality Assurance Engineer (QAE)

J. J. Fedick, Construction Engineer J. Goodbred, QAE G. Lauderback,-QAE

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D. L Marascio, QAE

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- M. J. McGill,^QAE F

P. L._ Naugle, Construction Enginaer

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H. ft.' Valters, Manager QA

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Bech[hlPowerCorporation

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A. Arch, Assistant Project Field Enginew (APFE)

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D. Blum, Staff Electrical Ennineer B. A. Drsgon, QAE H. D. Foster, Project Field Quality Control Engineer E. R. Klossin, Project QAE J. L. Martin, Lead Site QAE K. L. Quinter, Assistant Project Field Quality Control Engineer (APFQCE)

D. M. Shaw, APFE D. C. Thrynpson, APFQCE The above listed personnel attended exit interviews given on August 13 and 28,-1981. Other craftsmen, engineers, quality control technic' ens, and supervisors.were contacted as the inspection interfaced with their work.

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2.

Plant Tours (Unit Nos. 1 & 2)

Periodically during the inspection, tours were made of the Unit Nos.1 and 2 primary reactor containments, the reactor buildings, the control structure, and surrounding yards and shops. The inspector examined canpleted work, work in-progress, quality control activities, and equipment storece, handling, and maintenance.

He discussed the technical aspects of the work with craftsmen, supervisors, and engineers to assura work was being performed in accordance with requirements.

During the tou of the Unit No.1 and 2 control room, the inspector observed electricians testing and installing the grounds for flexible conduits used and i 10 CFR 50.55(grounding problem was identified under a 10 CFR 21 report in the PGCC. This a) Construction Deficiency Report. ibe inspector discussed the technical aspects of the work with the electricians and examined Field Disposition Instruction, F0hTNFV. The workmen appeared to be knowledgeable of the instructions and e. ware of the intent.

A review was made of the weld radigraphs for pipe spool DSB-203-1 which was the subject of a noncon:pliance (Reference:

IE Report 50-352/81-11). The radiograph for weld DB8-203-1 W2 had a linear indication in the weld area.

The licensee re-raciographed the weld and the review of the radiographs showed the weld to be acceptable.

No items of noncompliance were identified.

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3.

Licensee's Acticpns on Previous Inspection Findings (Closed) Unresolved Item (352/77-12-02, 353/77-12-02)

The NRC has reviewed the licensee's evaluation of the weld defects and concurs with the disposition (Reference: AITSF12189H1). This item is closed.

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(Closed) Unresolved Item (352/79-03-01, 353/71 33-01)

The RHR pump suction piping installation did not meet the design drawing requirements. Note 19 on GE drawing 761E292AD required a straight run of piping, prior to entering the pump, equal to 6 pipe diameters. The actual field installation did not meet this.

GE Engineering Change Notice NH-03460 deleted Note 19 based on a change in pump requirements. This is also reflected in the current edition of the FSAR, Figure 6.3-3, RHR System Process Diagram.

This item is closed.

(Closed) Unresolved Item (352/79-03-02, 353/79-03-02)

A discrepancy existed between the licensee's inspection program for temperature checks in the reactor pressure vessel (RPV) and the NSSS recommendations.

Subsequent to the NRC finding, Bechtel Corporation turned the vessel storage over to Reactor Controls, Inc., to install the vessel internals on January 1.1980.

On April 13, 1981, the Bechtel storage program was reactivated due.;to Reactor Controls withdrawal from the site.

The RPV storage requires, among other things, that close control and observation of humidity conditions be maintained. This is normally accomplished by a three pen temperature recorder which monitors the metal temperature at three elevations in the RPV.

In conjunction with this, a two pen recorder monitors the internal ambient air temperature and humidity.

Daily readings of these instruments are made to assure that condensation is not fonning on the RPV walls.

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At the time the Bechtel RPV storage program was reactivated, the

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necessary equipment was not available to take the daily temperature readings. The quality control storage inspector wrote an In-process Rework Notice, No. 1148, identifying *:.is proolem on April 27, 1981.

Daily tempe*ature readings were not taken, as prescribed by GE Specification 22A2517, paragraph 4.3.5.3 and the Maintenance Supplement sheet, dated March 30, 1979, on the RPV for Unit No.1 during the period of April 13, 1981 to approximately August 14, 1981.

This is an item of noncompliance (3E2/81-12-01).

The licensee had installed a part of the instrument system prior to the NRC's finding and had ordere:: the remainder of the necessary equipment.

The required equipment has been installed and the inspections reinstated.

The licensee held training classes for the quality control inspectors and the long tenn storage personnel to emphasize compliance with storage requirements.

In addition, a review was made of the RPV storage records to assure the other storage requirements were being performed in a timely manner.

The above items are closed.

(Closed) Unresolved Item (352/79-03-03)

The licensee's equipment storage inspection program is computerized such that cards are issued when a specified inspection is due.

If an inspec-tion is not performed within the alloted time, the delinquent inspection appears on the " Maintenance Action Required List (MARL)". Nonnally, items on this list are given priority for inspection.

In this particular case, it appeared to be a scheduling problem between the crafts, who provide access to the equipment, and the quality control inspector, who does the inspection. The scheduling problem was resolved and the inspection perfonned on April 12, 1979.

The NRC inspector reviewed the inspection records for the same attribute i

for the period September 14, 1978 to Ncvember 8,1979, and verified that the inspection frequer.cy was met.

He clso reviewed the MARL and verified i

that no Q-listed equipment exceeded reasonable delinquent periods.

This item is closed.

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(Closed) Unresolved Itsu (352/79-03-06)

Structural beams were over ground at the splice joints. The licensee issued Nonconfomance Report (NCR) 3503 which dispositioned the problem by adding splice plates over the joint areas. The NRC inspector verified that the repairs were made in accordance with the NCR by visually examining the joints on beams BilA and B2A (reference: vendor drawing 8031-C431-403A-6).

This item is closed.

(Clo*ed) Unresolved Item (352/79-04 02)

s Manufacturing problems were identified in the ITT Phillips Red Head concrete anchor bolts.

Some plugs were made with concave sides and others were made with cadnium plating rather than zinc. The licensee issued PECO Finding Report N-160 describing the problem. NCR's 3592, 3593, and 3736 were issued calling for inspections of warehouse stocks to identify nonconfoming plugs. The nonconforming plugs were replaced with acceptable ones by the manufacturer.

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The licensee perfomed tests on defective anchor bolt types to determine the severity of the problem. The test results indicate that the non-selfdrilling anchor bolts perfom satisfactorily and these are the type used at Limerick.

The inspector reviewed the test report and site purchase records to verify the licensee's findings.

This item is closed.

(Closed) Noncompliance (81-01-02) Welding of electrical supports to

heavy structural elements was perfomed without the required prehc-a'ing.

The licensee did the following to correct the noncompliance:

1) Held a training session on January 22, 1981 to retrain all personnel responsible for electrical welding preheat including quality control.

2) Revised Job Rule G-16 to more clearly describe the conditions

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under which preheat is necessary.

3) Reviewed industry codes, standards, and previous welding procedure qualifications to establish evidence for the support of non-preheat practices.

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The inspector reviewed the foregoing information and verified that training had been given as described and that Job Rule G-16 had been revised.

He requested that additional testing b.' performed on the cited weld and welds with similar joint configurations. This would provide added assurance that the lack of preheat was not detrimental to the materials.

The licensee perfomed magnetic particle testing of the cited weld and three others. All welds were acceptable.

This item is closed.

(Closed) Unresolved Item (352/81-04-05)

The weld filler metal did not appear to satisfy the requirements of ASME II Code, SFA-5.4 for the fillet weld test.

It was determined that the fillet weld test is an optional requirement and only required if the purchaser invokes it. The requirement was not invoked in this case.

This item is closed.

(Closed) Unresolved Item (352/81-04-03)

The weld joint preparation for the containment electrical penetrations did not appear to be testable by ASME III Code standards. The licensee perfomed preliminary tests and detemined that the joint design produced questionable test results. The weld end preparations have been changed to an open butt and the installed penetrations removed and remachined.

This item is closed.

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Construction De'iciency Reports (Closed) 76-00-01 Reactor Pressure Vessel (RPV) Fire l

The inspector reviewed the final report, " Assessment of Reactor Vessel

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Condition Subsequent to Fire in Cooldown Phase...," which describes L

the fire, the corrective actions, and the tests perfomed.

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the RPV records and verified that the damaged safe-end was replaced.

(Closed) 77-00-01 Cracked Reactor Building Beams The NRC staff reviewed the licensee's final report and concurred with the

l corrective actions taken (Reference:

AITS F12139H1).

These items are closed.

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Electrical Cables Emergency safeguard electrical cable pull lim 501BB was selected for observation of cable pulling activities. The inspector observed or verified the cable pulling activities such as:

1) Appropriate pull card documents 2) Quality control inspection 3) Cable size, routing, and lubricant 4) Precautions against damage to cable 5) Cable receipt inspection 6) Cable storage, handling, and control 7) Adequate procedures and specifications.

The following documents were reviewed or utilized in the inspection:

E 1412 Wire and Cable Notes and Details E 15 Single Line Meter and Relay Diagram 4 kv E 85 Schematic Meter and Relay Diagram 4 kv E 964 Cable Code Index E 1506 Electrical Circuit Schedule Job Rule E-3 Pennanent Plant Cable Storage and Maintenance It was noted during the pulling of cable 1AG501BB that the tensionometer, No. E229, had a calibration tag that stated an instrument accuracy of plus or minus 80 pounds. The pulling crew and quality control inspector stated, when asked, that field cable pulling tensions were made to the maximum loads allowed by the pull card. This means that cables could be overstressed by 80 pounds if the tensionometer was reading in the nonconservative direction.. This item is unresolved pending verification that no cabics have been overstressed and instrument error is considered in allowable cable pulling tensions (352/81-12-02).

The cable installation specification, Drawing 8031-E-1412, tables 2.3 and 2.4, provides for allowable tensile stress in cables.

In certain small size conductors, the pulling tensions are as low as 24 pounds. This relatively small value can easily be exceeded in even hand pulls. Unless difficulty is anticipated in a cable pull, pull tensions are not l

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recorded on pull cards. This item is unresolved pending provision of controls to preclude overstressing of low stress value cables (352/81-12-03).

The inspection of the outside bulk cable storage area disclosed six reels which had minor cable jacket damage to the extreme ends. The licensee tock immediate corrective action by removing the damaged section and recovering the cable end. He also initiated an audit, Audit Report No. E-091, of the cable storage area to assure compliance with requirements.

No items of noncompliance were identified.

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Welding Activities The inspector observed portions of the welding on the refueling bellows seal.

He performed a visual examination on the accessible side of the root weld and verified that a welder, symbol BK2, was qualified to perform the weld.

He also observed welding on portions of pipe support HBB-119-H17/1 and verified that the welder was qualified in accordance with ASME IX Code criteria.

No items of noncompliance were identified.

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7. ~ Unresolved 'Itens Unresolved items are matters about which more information is necessary in order to determine if they are acceptable, aeviations, or noncom-pliances. Unresolved items are discussed in paragraph 5.

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Exit Interview The inspector held exit interviews with members of the licensee's staff, listed in paragraph 1, on August 13 or August 28, 1981. He discussed the scope and findings of the inspection.

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