IR 05000388/1986025
| ML17146A643 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/04/1986 |
| From: | Anderson C, Chung J, Joe Golla NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17146A642 | List: |
| References | |
| 50-388-86-25, NUDOCS 8611130255 | |
| Download: ML17146A643 (7) | |
Text
Report No.
86-25 Docket No.
50-388 U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
License No.
NPF-22 Priority Category C
Licensee:
Penns lvania Power 8 Li ht Com an 2 North Ninth Street Allentown Penns 1 vani a 18101 Facility Name:
Sus uehanna Steam Electric Station Unit 2 Inspection At:
Berwick Penns lvania Inspection Conducted:
October 6-9 1986 Inspectors:
ph A Golla Rea tor Engineer
//-
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date M.
C un
,
ead a tor Engineer date Approve Cliffo J.
derson, Chief da e
Plant System Section, EB Ins ection Summar
- Ins ection on October 6-9 1986 Ins ection No. 50-388/86-25 Areas Ins ected:
Unannounced Safety inspection of Local Leak Rate Tests (LLRT.
Results:
No violations or deviations were identified.
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DETAILS 1.0 Persons Contacted t
"J. Blakesl ee, Jr., Assi stant Plant Superintendent
'T. Clymer, gA Supervisor - Operations J.
Dessoye, LLRT Technician
- M. Golden, Plant Engineering Supervisor
- B. Heslin, Power Production Engineer R. Kinney, LLRT Technician
- D. McGann, Compliance Engineer C. Smith, Sr. Results Engineer T. Smith, LLRT Technician T. Thomas, LLRT Technician D. Zeisloft, Foreman U.S. Nuclear Re ulator Commission L. Plisco, Sr.
Resident Inspector J.- Stair, Resident Inspector
" Denotes those present at exit meeting held October 9, 1986.
2.0 Local Leak Rate Testin LLRT The Technical port)on of ths s inspection was conducted to ascertain that LLRT was conducted in compliance with the requirements and commitments referenced in the following sections, and that the test results met the acceptance criteria specified in the station procedures and Appendix J,
CFR 50.
The procedures were reviewed for their technical adequacy.to perform the intended activities.
2.1 References Susquehanna Steam Electric Station Unit 2 Technical Specifications Section 3/4.6. 1
CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors Final Safety Analysis Report (FSAR)
ANSI/ANS 56.8-1981, Containment Systems Leakage Testing Requirements USNRC 18E Information Notice No. 85-71; Containment Integrated Leak rate Tests 2.2 Documents Reviewed
'AD-QA-502, Work Authorization System, Revision
AD-QA-522, Rework, Repair and Replacement of ASME Code Components, Revision
AD-00-540, Preventive Maintenance Scheduling, System, Revision
MT-GE-003, Limitorque Valve Actuator Maintenance, Revision
MT-GM-003, Valve Disassembly, Reassembly and Rework, Revision
MT-GM-021, Limitorque Type SMBOO-4 Operator Maintenance, Revision
MT-GM-028, Testable Check Valve Actuator Maintenance, Revision
AD-QA-423, Station Pump and Valve Testing Program, Revision
AD-QA-412, Leakage Rate Tests Program, Revision
PE-000-002, Operation of Leak Rate Monitors Model 14342 and Surge Tank Assembly, Revision
SE-259-027 LLRT FW Line B (part)
PENOX-9B, Revision
(LLRT Procedure)
2.3 Test Witnessin The inspector witnessed the performance of test activities to verify that:
approved test procedures were available and in use.
the procedures were adequately detailed to assure sati sfactory performance.
parts and materials were properly identified.
qualified test equipment and tools were use Portions of the Mass flow retest of feedwater flow check valve HV-241F032B were witnessed.
The valve had maintenance performed on it during this outage and then it was retested.
The valve exhibited a leak rate of 33.6 SLM.
This was judged by the licensee to be unacceptable.
The valve was reworked (hinge pin adjustment)
and retested.
The next test yielded a leak rate of 8.65 SLM.
The valve's hinge pin was adjusted a second time and another LLRT was performed.
The final leak rate for the valve was measured at 7.71 SLM.
The inspectors questioned the test mechanics about the system alignment.
It was concluded that the system was aligned such that a
valid test for the valve would result.
The inspectors noted that test personnel were using an approved test procedure, SE-259-027, and were qualified to conduct the test.
No unacceptable conditions were identified.
2.4 Administrative Control The inspectors interviewed selected licensee personnel and reviewed selected administrative procedures to verify the adequacy of the maintenance activities involving containment isolation valves (CIV's)
and containment penetrations.
Additionally a "Generic" licensee document pertaining to maintenance was reviewed as well as the main-tenance hi story for the current outage of the valve discussed in Section 2.3.
Administrative control of maintenance appears orderly and well established.
No unacceptable conditions were identified.
2.5 Test Results Local leak rate testing was in progress at the time of the.inspec-tion, therefore a final local leak rate total was not available.
The inspectors determined that the licensee is calculating the maxi-mum pathway leakage to be applied in the determination of the total local leak rate.
This is the accepted method of determining local leakage through a piping network per
CFR 50 Appendix J.
The inspectors discussed the provisions of IE information notice 85-71 "Containment Integrated Leak Rate Tests" with the licensee.
The licensee understood the provisions of the information notice with regard to the determination of an "As-Found" Leak Rate from a CILRT performed with containment pressure boundaries (CPB's) in an
"As-Left" condition.
The licensee has stated that they will implement the provisions of the information notice for future CILRT'.
The inspectors noted that the licensee does not have a written commitment to perform "As-Found" LLRT's on all CIV's and CPB's during a non-CILRT outage.
The "As Found" LLRT data is needed to quantify the total local leakage for the previous operating period.
This is utilized to evaluate overall containment integrity.
The licensee has stated they will provide a written document committing to the above by the end of the second quarter 1987.
This is an unresolved item pending final evaluation of the licensee commitment (86-25-01).
3.0 Personnel Trainin and uglification The qualifications and training records of (4) of (8)
LLRT repairmen and mechanics were audited by the inspectors.
In addition these same personnel were interviewed.
The inspectors determined that the qualifications of the test personnel interviewed met the requirements specified in ANSI N 18. 1-1971 "Selection and training of nuclear power plant personnel".
They were knowledgeable of their responsibilities and technical aspects of leak testing.
No unacceptable conditions were identified.
4.0 Containment Inte ratwd Leak Rate Testin CILRT Methodolo The licensee's CILRT corn utational met odo as d
s P
h logy w i cussed.
The Susquehanna Unit 2 containment was type A leak tested in June, 1986.
The licensee indicated that the leak rate had been calculated using both the Total Time Method (TTM) endorsed by topical report, BN-TOP-1 and acceptable per
CFR 50, Appendix J and the Mass Point Method (MPM) endorsed in ANSI/AN-56.8-1981.
The inspectors informed the licensee that TTM and Point-to-Point are the only methods specifically sanctioned in
CFR 50, Appendix J.
Licensee management was informed of the purpose and scope of the inspection at the entrance interview.
The findings were summarized at the exit meeting on October 9, 1986.
Attendees at the exit meeting are listed in section 1.0 of this report.
At no time during the inspection was written material provided to the licensee by the inspector II
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