IR 05000311/1978045

IE Insp Rept 50-311/78-45 on 781116-17.No Noncompliance Noted.Major Areas Inspected:Containment Integrated Leak Test Procedure & Local Leak Rate Testing

ML18078A632
Person / Time
Site:	Salem
Issue date:	11/29/1978
From:	Caphton D, Higgins J, Tanya Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18078A631	List: IR 05000311/1978045 ML18078A630
References
50-311-78-45, NUDOCS 7901110011
Download: ML18078A632 (5)

Text

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report No. 50-311/78-45 Docket N.....:...:~_.....,_ __ _

Region I License N CPPR-53 Priority ------

Category Bl

_..........., ____ _

Licensee:

Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101

• Facility Name: Salem Nuclear Generating Station, Unit 2 Inspection at: Hancocks Bridge, New Jersey Inspection conducted:

November 16-17, 1978 Inspectors:

Approved by:

Inspection Summary:

Inspector Reactor Inspector on, Chief, Nuclear Support 1, RO & NS Branch date signed 11 /29 /7f{

date signed

• date signed

~(

Inspection on November 16-17, 1978 (Report No. 50-311/78-45)

Areas Inspected: Routine, unannounced inspection by regional based inspectors of the containment integrated leak rate test procedure, local leak rate testing and licensee action on previous inspection finding The inspection involved 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> on site by two NRC regional based inspector Results: No items of noncompliance or deviations were identifie Region I Form 12 (Rev. April 77)

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DETAILS Persons Contacted The below listed technical and supervisory personnel were contacte Public Service Electric and Gas Company

• S. Chawaga, Project QA Engineer

• J. Cox, Senior Construction Engineer, Startup

• R. Griffith, Senior Staff Engineer, QA K. Kieper, Materials Test Engineer

• E. Meyer, Project QA Engineer F. Twogood, Lead Shift Test Engineer

• • united.Engineers and Constructors

. *F. Albert, Startup Engineer M. Juister, Mechanical Test Engineer

• R. Phelps, Field Superintendent, QC

• D. Snyder, Project Engineer

• E. Walsh, Assistant Field Superintendent, QC

• denotes those present at the exit intervie The inspector also talked with and interviewed several other mem-bers of the engineering and technical staff *previous Inspection.Item Update

{Open) Unresolved Item (311/78-29-01): The licensee's representative has acknowledged that Type C retests are required after maintenance is performed on a valve, but no formal mechanism has yet been established to ensure that this is accomplishe (Open) Unresolved Item (311/78-29-02):.The licensee's representative stated t_hat administrative controls would be established, but that they had not been completed as of this inspectio (Open) Unresolv~d Item (311/78-29-03): The licensee's representative stated that the RHR system valves SJ49, RH26, and RHl and the containment purge system butterfly valves were the only reverse direction tested valve The test on the butterfly valves appeared of equivalent conservatis The test of the RHR valves may not be an Appendix J required Type C test. This item will be reviewe further with NRC management in conjunction with the below ite (Open) Unresolved Item (311/78-29-08): The licensee's representative stated that since these valves are only cycled once postaccident to shift from the injection to the recirculation mode and maintained that they should not be Appendix J testable valve This item will receive further review by NRC managemen (Open) Unresolved Item (311/78~29-04): The inspector reviewed sixteen field changes to SUP-DTP-30-LRT-2 which accomplished the majority of the required venting and drainin Change 11 dated September 9, 1978 contained the bulk of these change The licensee's representative stated that they did not plan to.use any test method other than the primary one detailed in the procedure. *The inspector noted that proper procedural guidance was still not provided relative to the venting and draining the service water lines to the contain-ment fan coolers (PenetrationsA9,~~5'4;=etc:}.

(Open) Unresolved Item (311/78-29-07): The licensee's representative stated that discussions with the instrumentation vendor are continuing, but that no documentation has yet been receive.

Containment Integrated Leak Rate Test (CILRT) General The inspector reviewed the following procedures associated with the. CILR LRT-3, "Reactor Containment Type A Leakage-Rate Test Procedure, 11 dated October 2, 1978 (draft).

• DTP 30-SIT-l, "Reactor Containment Structural Integrity Test, 11 dated November 14, 197 These procedures were reviewed for proper format, technical adequacy and compliance with 10 CFR 50 Appendix J and ANSI N4 The SIT procedure was reviewed only for CILRT related item With the exception of the below items the inspector had.; no further questions on the procedure CILRT Procedure The below items associated with the review~~* procedures are unresolved and are collectively designated as item no. (311/

78-45-01).

(l} Test Duration The procedure has a provision which allows the test to run less than 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ANSI N45.4 requires a test duration of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless it can be shown that an accurate leakage rate can be obtained from a shorter test. It is the NRC's position that a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test is required to insure an accurate and representative leakage rate determinatio *

(2)

Absolute Values The current procedure has no prov1s1ons for calculating leakage rates using absolute values corrected for instru-ment error as required by Section III.A.3.C of Appendix (3)

Vapor Pressure The procedure allows a partially completed test to con-tinue with dew point instrumentation inoperative due to failur ANSI N45.4 requires that the' d~w**point* be* measure (4)

Volume Changes The procedure contains no prov1s1on for monitoring con-tainment sump level change An increase in sump level, reducing containment free volume, could mask CILRT leakag (5)

Valve Lineups (a)

Penetration l8C: The containment isolation valv~s of this penetration require venting outside containment during the CILR No vent path is specified in the current procedur (b)

Penetration 36: The current valve lineup creates a leak path through vent and drain line (6) Acceptance Criteria (_7)

Section V.B.3 of Appendix J specifies the requirement for analysis and interpretation of CILRT results. The inspector also informed the licensee of the NRC position regarding the acceptance criteria of the CILR The measured leakage rate at the 95% upper confidence

• level plus required Type C leak rate additions must be less than 0.75 L Venting and Draining Systems as described in Appendix J paragraph III.A. which rupture as a result of the loss of coolant accident must be vented and drained for the CILR If not, Type C leakage of the isolation valves must be added to the CILRT results prior to comparison with the acceptance criteri (e.g. Component Cooling Water and the Fire System)

!.

(

.,.

The below item will receive further NRC review and is desig-nated as inspector follow item (311/78-45-02).

(8)

Data Rejection During the CILRT data may be rejected as an outlier provtded a definitive data rejection criteria has been established. Currently, there is no such criteria in the procedur.

Unresolved Items Items about which more information is required to determine accepti-bility are considered unresolve Paragraph 3.b of this report contains unresolved item.

Exit Interview At the inspection's end the inspector held a meeting (see paragraph 1 for.attendees} to discuss the inspection scope and finding The unresolved items were. identifie _I