ML18079B003

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IE Insp Repts 50-272/79-20 and 50-311/79-32 on 790530-0601.No Noncompliance Noted.Major Areas Inspected: Unit 1 Containment Integrated Leak Rate Test Procedure & Unit 2 Containment Integrated Leak Rate Test Rept
ML18079B003
Person / Time
Site: Salem  PSEG icon.png
Issue date: 08/02/1979
From: Caphton D, Tanya Smith
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18079B002 List:
References
50-272-79-20, 50-311-79-32, NUDOCS 7910010371
Download: ML18079B003 (5)


See also: IR 05000272/1979020

Text

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U.S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

Region I

Report No. 79-20/79-32

Docket No. 50-272/50-311

License No. DPR-70/CPPR-53

Priority:

Category:

C

Licensee:

Public Service Electric & Gas Company

80 Park Place

Newark, New Jersey 07101

Facility Name:

Salem Nuclear Generating Station, Unit 1 & 2

Approved by:

Inspection Summary:

- June l , 1979

Inspector

Chief, Nuclear Support

RO & NS Branch

date signed

1'/2hcz

  • crate s i gned

Inspection on May 30, 1979 to June 1, 1979 (Co~bined Report.Nos.

50-272/79~20 and 50-311/79-32

Areas Inspected:

Routine, unannounced inspection by a regional based

inspector of the Unit l containment integrated leak rate test procedure;

and licensee action on previous inspection findings; and the Unit 2

containment integrated leak rate test report.

The inspection involved

20 inspector-hours (Unit 1 - 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, Unit 2 - 10 *hours) on site by

one NRC regional based inspector.

Results:

No items of noncompliance were identified.

9*

- 2 -

DETAILS

1.

Persons Contacted

2.

The below listed technical and supervisory personnel were con-

tacted.

B. Canfield, Maintenance Supervisor

K. Kieper, Material Test Engineer

  • M. Metcalf, QA Engineer, Resident Group
  • E. Meyer, P*roject QA Engineer

J. Stillman, Station QA Engineer

  • J. Zupko, Chief Engineer

, *Denotes those present at the exit interview.

Licensee Action on. Previous Inspection Findings

(Closed) Open . .Item (272/79-10-01):

The inspector revi'ewed the

latest draft of"the containment integrated leak rate test (CILRT)

procedure SP.Co) *4.6.1.2, "Containment System - Type A lnteg:rel\\ted

___ ,

Leak Rate Test Unit No. 1

11

The resolution of each part of t11*e*

open item i's presented below as numbered in the initial report.

(1)

The procedure has b~en revised to require

that the test be run for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(2)(3) The Acceptance criteria and data evaluation

technique for the CILRT have been revised to

reflect current NRC positions.

(4)

An adequate warning statement has* been added to

the procedure concerning leak repairs during the

test.

(5)(6) Provisions have been made in the procedure to

require maintaining an events *log, and to log

hourly atmospheric data as required by ANSI N45.4.

(7)

Th~ procedure has been revised to require that

test data be corrected for instrumental error as

required by lOCFR50 Appendix J.

3.

(8)

(9)

( l 0)

- 3 -

The procedure requires that reactor coolant

systems and containment sump level changes

be measured over the duration of the test.

Level changes will be evaluated, and a

correction made to the measured leak rate

as required.

A data sheet has been incorporated into the

procedure for recording instrument volume

weighing factors. A plan has been included

outlining the procedure which will be used

to reassign those factors due to instrument

failure during the test.

Penetrations not vented and drained as

required by 10CFR50 Appendix J are listed

in the procedure.

Type C test leakage of

those penetrations will be added on to "the

measured leak rate prior to comparison with

the acceptance criteria.

(11) Data rejection criteria have been added to the

procedure.

CILRT Valve Lineups

The inspector reviewed the valve lineup portion of procedure

SP(o) 4.6.1.2, "Containment System - Type A Integrated Leak Rate

Test Unit 1

11

, and verified that a valve lineup* was provided

for all systems penetrating the containment, penetrations were

drained and vented as required by 10CFR50 Appendix J and that

no artificial leakage barriers or leakage paths were created.

The inspector identified no discrepancies in thi~ review and

has no further questions in this area at this time.

4.

Containment Integrated Leak Rate Test

a.

Genera 1

The following documents and procedures were reviewed by

the inspector:

11Report on Reactor Containment Integrated Leak Rate

Test Unit No. 2

11

, dated May 29, 1979.

.. ..

)

- 4 -

DTP 30-LRT-3, Revisfon 0,

11Reactor Containment Type A

Integrated Leak Rate Test

11 dated December 12, 1978.

The above references were reviewed for accurate data trans-

cription, proper implementation of procedural changes,

. correctness of the* analytical methods, and the accur.ate

recording of significant events during the test.

No items

of noncompliance*were identified.

b.

Satisfactory CILRT

  • Using raw data, the inspector independently calculated the

containment leak rate.

The results are presented in Table

1. The inspector's independent leak rate calculations

confirm the licensee's report of a successful CILRT.

5.

Exit Interview

At the fospection's end, the inspector held a *meeting (-See Detail

1 for attendees) to discuss the inspection scope and findings ..

No items of noncompliance were identified and there were no

unresolved items.

Item

1.

2.

3.

4.

5.

TABLE 1

December 1978 - CILRT Conducted at Pa (47 PSIG) at Salem Nuclear Generating Station Unit 2

Acceptance

Criteria

Containment Leak Rate

(Mass Point) -

Upper 95% Confidence Level

on Leak Rate (Mass Point)

Local Leak Rate Test

Additions (Type B & C)

Containment Leak Rate at

Upper 95% Confidence Level

Plus Required Additions

0.75La = .075

Supplemental Verification

Test Difference

0.25La = :025

Reported

Results

0.0309

0.0354

0.0002

0.0478(2} -

0.024

Inspector*s-

Findings

0.031

0.035

0.0002

0.048

0.024

Notes:

(1)

All data reported in weight percent per day.

(2)

Includes 0.0122 weight percent per day from instrument error analysis irl lieu

of correcting raw data for instrument error.

-

./