IR 05000369/1986025

Insp Repts 50-369/86-25 & 50-370/86-25 on 860814-20.No Violations or Deviations Noted.Major Areas Inspected: Containment Integrated Leak Rate Test & Followup of Outstanding Items

ML20215N140
Person / Time
Site:	McGuire, Mcguire
Issue date:	10/21/1986
From:	Jape F, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20215N135	List: IR 05000369/1986025 ML20215N134
References
50-369-86-25, 50-370-86-25, NUDOCS 8611040349
Download: ML20215N140 (8)

Text

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Report Nos.: 50-369/86-25 and 50-370/86-25 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 .- Docket Nos.: 50-369 and 50-370 License Nos.: NPF-9 and NPF-17 Facility Name: McGuire 1 and 2 Inspection Conducted: August 14-20, 1986

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Inspector:  ; I, // uNau /S - Z-4 - SZ H. L. Whitener ~

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Oate Signed Approved by: 44 /d 2//[[ F. Jape, Section Chief

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    (/ /  Date Signed Engineering Branch Division _of Reactor Safety

SUMMARY Scope: This routine, announced inspection involved witnessing the containment integrated leak rate test and followup of outstanding item Results: No violations or deviations were identified.

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l f , REPORT DETAILS Persons Contacted ' Licensee Employees

 *B. H. Hamilton, Superintendent, Technical Services
 * M. Sample, Superintendent, Integrated Scheduling
 *R. B. Travis, Superintendent, Operations
 *D. S. Marquis, Performance Engineer
 * M. Suslick, Performance, General Office
 *R. A. Johansen, Test Engineer
 *D. N. Smith, Nuclear Production Engineer P. W. Roberson, Nuclear Production Engineer
 *E. D. McCraw, Compliance Engineer
 *N. G. Atherton, Compliance
 *W. E. Smith, Mechanical Maintenance
 *T. M. Cook, Mechanical Maintenance
 .NRC Resident Inspector W. T. Orders, Senior Resident Inspector
 * Attended exit interview Exit Interview i

The inspection scope and findings were summarized on August 20, 1986, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding No dis-senting comments were received from the license The following ' item was identified during this inspectio IFI (50-369/86-25-01 and 50-370/86-25-01), Review licensee action

relative to formalizing the methods for inspection' of piping supports and restraints after a plant transient (paragraph 6.c).

The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this. inspectio . Licensee Action on Previous-Enforcement Matters (92702)

 (Closed) Violation (50-369/81-03-04) related to the failure to have ' a procedure to establish containment integrity for core alteration This violation was identified in IE Inspection Report 50-369/81-0 .
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The same report (paragraph 10) states that the licensee suspended refueling operations, developed a procedure and verified valve alignments for con-tainment integrity per this procedure (PT/1/A/4E00/02C) prior to continuing refueling operation It appears that the violation was corrected and closed out in the same report. The inspector verified that these procedures are current for both Units 1 and 2 and have been periodically updated to q reflect changes in plant systems. This item is close . Unresolved Items Unresolved items were not identified during the inspection.

4 Containment Integrated Leak Rate Test - Unit 1 (70313) The inspector reviewed and witnessed test ' activities to determine that the primary containment integrated' leak rate test (CILRT) was performed in i accordance with the requirements of Appendix J to 10 CFR 50, ANSI 45.4 and

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the test procedure PT/1/A/4200/01A, " Containment Integrated Leak Rate Test and Structural Integrity Test."

Selected sampling of the licensee's activities which were inspected included: (1) review of the test procedure to verify that the procedure was properly approved and conformed to the regulatory requirements; (2) observa-tion of test performance to determin e that test prerequisites were com-pleted, special equipment was installed, instrumentation was calibrated, and

appropriate data were recorded; and (3) preliminary evaluation of leakage rate test results to verify that leak rate limits were me Pertinent aspects of the test are discussed in the following paragraph General Observations The inspector witnessed and reviewed portions of the test preparation, containment pressurization, temperature stabilization and data pro-cessing during the period of August 14-20, 198 The following items were verified:

-(1) The test was conducted in accordance with an approved procedure.

, Procedure changes and test discrepancies were prcperly decuaented in the precedur (2) Test prerequisites selected for review were found to be complete (3) Selected plant systems to maintain test control were reviewed and ' found to be operational.

) -(4) Calibration and location of special test instrumentation was i discussed with the licensee and found to be acceptable.

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(5) A containment temperature survey was performed using a Specia Test Procedure to confirm that RTD weighting factors are represen-tative of the RTD location (6) Data required for the performance of the containment leak rate calculations were recorded at 10 minute interval (7) Problems encountered during the test were described in the test event lo (8) Containment air compressors were isolated and vented for the tes No violations or deviations were identified in the above areas.

] b. Containment Integrated Leak Rate Test - Method , l The integrated leak rate test was performed using the absolute method i based on measurement of containment air temperature, pressure, and j vapor pressure at ten-minute intervals for a period of 24 hour A

four-hour supplemental test was performed subsequent to the 24-hour

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Type A test to confirm containment atmospheric stabilization ' and instrument accurac The licensee has developed a program for the mass point-linear regres-sion method of analysis of the mass data in accordance with the _ equa-tions of ANSI-N5 Results of this analysis and a total time analysis in accordance with ANSI-N45.4 are discussed in paragraph below.

I c. Containment Integrated Leak Rate - Test Results (Unit 1) A 24-hour containment integrated (Type A) leak rate test and a four-hour supplemental leak rate test were performed on the Unit 1 primary containment in the period August 16-17, 198 Mass point-linear regression analysis was used by the licensee to determine the leak rate (Lam) and upper confidence limit (UCL) at 24 hours. The test met the acceptance criteria for both mass point and total time analysis as shown below; the values are expressed as weight percent per da Mass Point Total Time wt%/ day wt%/ day La .3 (allowable leakage) 0.75 La 0.225 0.225 (test acceptance limit) Lam at 24 hr .149 0.115 UCL at 24 hr .153 0.168 A four-hour supplemental test was performed in accordance _ with the recommendations of Appendix C of ANSI N45.4-1972. The measured com-posite leak rate was within the upper and lower acceptance limits _

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specified by the equation: Lam + Lo - 0.25 La < Lc < Lam + Lo + 0.25 La for the mass point analysi The values for the equation by mass point analysis in terms of weight percent per day are as follows: wt%/ day Composite leak rate, Lc 0.424 Type A test leak rate, Lam 0.149 Imposed leak rate, Lo 0.2446 Error limit, 0.25 La 0.075 Substitution of these values into the acceptance equation demonstrate that the specified inqualities are satisfied as follows: 0.3187 < 0.424 < 0.4686 d. Containment Integrated Leak Rate Test Events Listed below are excerpts from the test log which summarize the test events: Date Time Comment 7/29 0930 Structural integrity inspection of containment vessel and reactor building was initiate /4 1600 Containment vessel and reactor building inspection was completed. No significant problems were identifie /14 2100 Began pressurization of the containmen /15 0500 Containment was pressurized to 29.6 psi /15 1030 Temperature stabilization was achieve ,

8/16 0250 Excessive leakage was identified as an improper valve alignment on the secondary system and corrected. Four-hour tempera-ture stabilization criteria satisfied from 2250, 8/15 to 0250, 8/1 /16 0257 Time zero for the Type A test is 0257 hour /17 0303 Type A test is terminated with an accep-table leak rate by both mass point and total time calculation _ _ _ . - ___ _

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1 0343 Imposed leak rate is established and supplemental test start is initiated Lo = 4 scfm (80% La).

0744 Supplemental test is terminated.

i As-Found Leak Rate The inspector discussed the status of the program for determination of the as-found containment leak rate with licensee personnel, but did not

review the specific data at this time. The unit status is discussed belo Unit 1

Control for obtaining the as-found leak rate for Unit I was reviewed at a previous inspection and reported in IE Report 50-369/86-16 and 50-370/86-16. An inspector followup item 50-369/86-16-01 was identi-fied at that. inspection. The -licensee stated that the administrative < controls involved to obtain the leak rate prior to- any maintenance - which could change the valve leakage had worked well, tHt have not yet-been formalized into a plant procedure. Preliminary results indicate an acceptable as-found leakage, but the final evq1uation .is not yet j complet IFI 50-369/86-16-01 remains open.

Unit 2 A ' violation 50-370/86-16-01 was previously issued concerning the , failure to perform the as-found leak rate. Since that inspection, the licensee has conducted a review of all maintenance performed on valves , prior to leak rate measurement. It appears that' preventive maintenance

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before leakage measurements was -done in fewer ' instances than was initially estimate The investigation indicates that in most j instances, the preventative maintenance can be shown to not affect valve leakage. This review is still in progress and will be reviewed .! at a future tim Violation 50-370/86-16-01 remains ope , Results of the Followup Inspection of Outstanding Items (92701)~ '

. (Closed): IFI (50-369/82-16-02) concerned the licensee's commitment to establish a method of tracking and implementing commitments to the NRC and documenting closecut corrective action To accomplish the above, the licensee established the McGuire Action Directory (MAD). This system of tracking and closing out action items is implemented by Station Directive 3. The inspector found the system in operation and useful in determining the status of outstanding
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       .I items' reviewed during this inspectio This item is close l
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b. Followup Inspection Items (IFI) 50-369/83-35-01, 83-35-02 and 83-35-03 relate to identification of damage to piping supports and restraints subsequent to a plant transient, repair of the supports and restraints and development of a procedure for inspection of these supports and restrains after plant transient The. status of these items is as follows:

 (1) Closed: IFI (50-369/83-35-01) concerns completion of the review of TP/0/A/1200/27, Piping Dynamic Response Following Loss of Electrical Load, and identification of any damaged supports and restraint The McGuire Action Directive (MAD) item 1301-029 documents com-pletion of the procedure review and identification of six damaged I supports and restraints for repair and reinspectio Identifica-tion of the damage is further supported by MOAG - Problem Report -

McGuire 83-05, which identifies the nature of the damage and the recommended corrective action. This item is close (2) Closed: IFI (50-369/83-35-02) concerns - repair of the damaged i supports and restraints. The licensee committed to repair the

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supports and restraints by 11/18/83. The schedule was subse-t quently changed to 6/1/84, by a letter to the NRC identifying the delay as necessary for completion of redesign wor MAD item 1301-030 documents the repair to the damaged supports and restraints. The repair to the supports and restraints is further supported by Nuclear Station Modification (NSM) process record The inspector review a sample as follows: Record Support / Restraint Completed MG-1-1461 CFH44 4/25/84 MG-1-1363 SMH36 2/2/84 SMH38 2/2/84 MG-1-1361 CPH24 12/21/83 This item is close (3) Closed: IFI (50-369/83-35-03) concerns the development of a procedure for inspecting supports and restraints af ter p,lant transient The licensee had developed a procedure TP/0/A/1200/27 for inspec-tion of piping supports and restraints for use after a plant transient during startup testin Subsequent to support and restraint damage, the licensee developed a procedure for reinspec-tion of the plant supports and restraints, TP/1/A/1200/27A. MAD item 1301-031 documents the development of TP/1/A/1200/27A. The inspector verified that TP/1/A/1200/27A is in the plant master i

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.I file The inspector concluded that the action taken by the licensee addressed the immediate concern relative to plant tran-

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sients in the startup testing phase of plant operation but does not adequately address the inspection of supports and restraints in the routine plant operation This item is closed and a new Inspector Followup Item is identi-fled, based on review of current plant practices, in paragraph below, Open: IFI (50-369/86-25-01) and (50-370/86-25-01) The inspector discussed the current practice for inspection of supports and restraints after a plant transient with plant personnel. The lic~nsee e , stated that subsequent to a unit trip or identifiable transient a  !

:   walkdown and visual inspection is performed on suspect systems. At any
  . time, a damaged support is identified a nonconforming item report is

- processed and Design Engineering is contacted for evaluation of the problem. Design Engineering will define further inspection areas and

,   determine the operability status of the component and system. _ Guide-

' lines for accomplishing these inspections and evaluations were provide to the plant by Design Engineering in a letter dated January 23, 198 The inspector concluded the licensee has established a method of

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inspecting supports and restraints and evaluating the consequences of damage; however, the methods should be more formally specified in a

;   plant procedure. Such a procedure may also serve as documentation of
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the transient, and results of the inspection, date and time of the

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inspection, personnel involved in the inspection, evaluation and time

!   frame of system operability and completion of corrective action. While recognizing that all plant transients are not immediately detectable the procedure should define those transients which are recognizable and
;   based en plant experience expected to result in damage to supports and
!   restraint !

At the exit interview, licensee management agreed to evaluate this matter. The matter was identified for inspector followup as: IFI (50-369/86-25-01) and IFI (50-370/86-25-01): Review licensee < action relating to development of a plant procedure for inspection of supports and restraints after a plant transien Closed: (LER 84-08, Units 1 and 2) concerned a nonconservative error i in the analysis of the main steamline break (MSLB) which could result in containment temperature higher than that . initially calculated .and therefore has the potential to impact equipment qualificatio This problem was reviewed by Nuclear Reactor Regulatio A Safety Evaluation Report was i ssued (8/13/86) in which the staff concurred with the licensee's evaluation that the higher temperatures generated in the event of an MSLB will not affect the ability to shut down the reactor and maintain it in a safe shutdown conditio This item is closed.

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