IR 05000414/1985037

Insp Rept 50-414/85-37 on 850903-06.No Violations or Deviations Noted.Major Areas Inspected:Review of Hot Functional Test Procedures & Observation of Thermal Expansion Test Performance

ML20132B224
Person / Time
Site:	Catawba
Issue date:	09/19/1985
From:	Jape F, Lenahan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20132B217	List: IR 05000414/1985037 ML20132B212
References
50-414-85-37, NUDOCS 8509260129
Download: ML20132B224 (4)

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~ UNITED STATES WA Mco,D

/ o NUCLEAR REGULATORY COMMISSION REGION 11

[ p g j 101 MARIETTA STREET, * 2 ATLANTA, GEORGI A 30323

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Report No.: 50-414/85-37 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket No.: 50-414 License Nos.: CPPR-117 Facility Name: Catawba Unit 2 Inspection Conducted: September 3 - , 1985 Inspector: h A e 9 f6 J. J. Lenaharf g " Date Signed Accompanying Personnel: L. E. Nicholson Approved b C N b u b f e d b " " & T-/ 9 ~ VC F. Jape, Section Chief 't Date Signed l

Engineering Branch Division of Reactor Safety SUMMARY Scope: This routine, announced inspection entailed 54 inspector-hours on site in the areas of review of hot functional test procedures, observation of thermal expansion text performance, observation of testing of main steam safety relief valves, and review of results of main steam safety relief valve testing and thermal expansion testin Results: No violations or deviations were identifie gq2}Ofs O

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REPORT DETAILS Persons Contacted Licensee Employees W. L. Anfin, Mechanical Maintenance Support Engineer J. Gilreath, Assistant Engineering Mechanical Maintenance

• J. W. Hampton, Station Manager

• P. G. LeRoy, Licensing Engineer S. Mays, Assistant Engineer, Mechanical Maintenance Other licensee employees contacted included three engineers and eight technician NRC Resident Inspector

• P. K. Van Doorn

• Attended exit interview Exit Interview The inspection scope and findings were summarized on September 6,1985, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the licensee. The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during the inspectio . Pre-0perational Testing of Main Steam Safety Relief Valves (92706)

The inspectors reviewed Duke procedure number TP/2/A/1250/05, " Pre-operational Test of Unit 2 Main Steam Coded Safety Relief Valves." This procedure provided the test method, test data to be recorded, acceptance criteria, and detailed test procedure required to deterraine the actual set pressure of the safety relief valves prior to startup of Unit The acceptance criteria was based on the set pressures specified in the draft

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l of Unit 2 Technical Specification 3.7.1.1. The inspectors witnessed testing i

of safety relief valve numbers 2SV-11 and 2SV-17. After completion of

, testing, the inspectors reviewed the test data for the 20 main steam safety i

relief valves and verified test data were recorded in accordance with test procedure requirements, and that setpoints of the relief valves met the test acceptance criteria (proposed Technical Specification set pressure).

Within the areas inspected, no deviations or violations were identified.

i Themal Expansion Test (70370)

i The inspectors examined the thermal expansion test procedures, observed portions of the thermal expansion test, and reviewed test data. Acceptance criteria utilized by the inspectors appear in Final Safety Analysis Report

(FSAR) Section 3.9.2.1.2 and FSAR Table 14.2.12.1.

J Review of Thermal Expansion Test Procedures i

j The inspectors examined test procedure number TP/2/A/1150/08, Thermal Expansion Testing on ASME Code Piping. This procedure covers testing of Duke Classes A, B, and C piping (ASME Classes 1, 2, and 3 piping, respectively) with the exception of the primary loop NSSS piping. The inspector verified test prerequisites were specified, test instructions

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and objectives ~ were clearly stated, and acceptance criteria were specified. The test acceptance criteria requires that snubbers not be

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within 1/2-inch of either piston stop during the test, that spring load

settings be within plus or minus ten percent of the values given on

. .the as-built drawings, and that piping and components not contact any l interference which may restrict piping expansion.

i The inspector also examined procedures which control thermal expansion testing of the prima:y loop piping. These procedures were as follows:

j (1) Specification Number CNS-1144.05-00-0017, Specification for Shimming of Major NSSS Equipment Supports and Reactor Coolant System - Themal Expansion Monitoring, Unit 2

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(2) Construction Procedure Number CP-762, Thermal Monitoring - Unit 2 Observation of thermal Expansion Test The inspectors walked down portions of the reactor. coolant (NC) syste During the walkdown, the NC system was operating at a temperature of between 545 and 555* The inspectors verified that temporary

scaffolding and ladders and permanent plant equipment (HVAC ducts and equipment, cable tray supports, other piping, structural steel, whip

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restraints, etc.) did not interfere with piping thermal movements. The inspectors also made a detailed inspection of the NC piping in Math i Models NC-206, NC-207, NC-210, and NC-213 and verified type and number

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of supports were as shown on design drawings, verified spring can and

> snubber settings were accurately recorded by licensee inspectors, and verified that the licensee inspectors identified potential interference to thermal movements and recorded the potential interferences as

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required by the test procedur c. Review of Test Results The inspectors reviewed data documenting the results of thermal expansion testing of the reactor coolant system for piping in Math Models NC-203, NC-204, NC-205, NC-206, NC-207, NC-210, NC-212, NC-213 and NC-231. This data included cold load setting of spring cans and snubbers at ambient temperature, identification and resolution of potential interferences to thermal movements identified at ambient temperatures, hot load setting of spring cans and snubbers at. test temperature, and identification of potential interference at test temperatur Within the areas inspected, no deviations or violations were identified.

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