IR 05000272/1986014
| ML18092B180 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/10/1986 |
| From: | Anderson C, Chung J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18092B179 | List: |
| References | |
| 50-272-86-14, 50-311-86-14, NUDOCS 8606160163 | |
| Download: ML18092B180 (8) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No /86-14, 50-311/86-14 Docket No, 50-311 License No DPR-70, DPR-75 Category C Licensee:
Public Service Electric and Gas Company Facility Name:
Salem Nuclear Generating Station, Units 1 and Inspection At:
Hancock's Bridge, New Jersey Inspection Conducted:
April 28 - May 2, 1986 Inspector:
f Engineer G-10-86 date Approved by:
b - I0-86 f w Plant Systems date Inspection Summary:
Inspection on April 28 - May 2, 1986 (Combined Report Nos. 50-272/86-14 and 50-311/86-14).
Areas Inspected:
Routine, unannounced inspection of followup of previous inspection findings; evaluation of Local Leak Rate Testing (LLRT) results; and facility tour Results:
No violations or deviations were identified.
DETAILS 1.0 Persons Contacted
- C.J. Conner, Jr., ISI Supervisor, Salem *I_. Lake, ISI Engineer R.S. Patwell, Licensing and Regulations
- D.A. Perkins, Station QA Manager
- J. Rupp, Licensing Engineer W. Treston, ISI Supervisor, Salem Operation
- P. White, Maintenance Manager, Salem Operation
- J.M. Zupko, Jr., General Manager, Salem Operation The inspector also interviewed other licensee employees during the course of inspectio *Denotes those present at the exit interview on May 2, 198.0 Licensee Actions on Previous Inspection Findings (Closed) Unresolved Item (50-272/84-28-01) No 11As Found 11 ILRT calculation As Found 11 and 11As Left 11 ILRT calculations were included in the 1984 ILRT report submitted to NRC on November 8, 198 The 11As Found 11 ILRT was obtained by taking the difference between the 11As Found 11 and the 11As Left 11 Type C LLRT and by adding the difference to the 11As Left 11 I LR The resulting 11As Found 11 ILRT still met the acceptance criterion of 216.240 SCCM (La).
This correction was implemented into Type A test procedure, M9-ILP-CT-l, Revision 4 by issuing an Advanced Change Notice (ACN), dated May 1, 198 This item is close (Closed) Unresolved Item (50-311/83-17-01) Correction of ILRT 11As Left" resul The I LRT results reported to NRR on October 13, 1983 included 11As Left
and 11As Found" type B and C test result The ILRT correction for 11As Found 11 value as per NRC IE Information Notice 85-71, was implemented in procedures, M9-ILP-CT-l and M9-ILP-CT-3, by issuing two CN 1 s A both dated May 1, 198 This item is considered close (Closed) Inspector Followup Item (50-311/83-17-03) Corrections For The Preliminary ILRT result Pre-test and post-test volume corrections were included in page 13, section 6 of the final ILRT report submitted to NRC on October 13, 1983.
Also, systems and penetrations isolated during the ILRT test were type C tested and the corrections for 11As Found" ILRT were included in section 6.2 of the repor The effect of pressurizing steam generators #22 and
- 23 was evaluated and also included in the October repor Based on the above review, this item is close (Closed) Deviation (50-272/84-26-02) Excessive leakage from steam generator blowdown isolation valve The licensee identified the excessive leakage through containment isolation valves ICC215, 14GB4 and IVC8, and issued LER 83-010/03L, March 8, 198 Subsequently, a change to technical specification Table 3.6.-1 was proposed to NRR on November 27, 1985 for an exemption from the type C tes The licensee 1 s response letter of November 5, 1984 to the Notice of Deviation was reviewed, by the inspecto It was determine that closure of this item would depend upon the final approval of the proposed change to the technical specifications, Table 3. Based on this, this item was closed and combined with items 50-272/84-26-03 and 50-311/83-17-02, and modified as an unresolved item, pending final approval of the proposed changes by NRR (see paragraph 3.3).
(Closed) Unresolved Item (50-272/84-26-03 and 50-311/83-17-02) venting of containment weld channel The licensee proposed an exemption of Weld Channels venting by a letter dated October 13, 198 This item was closed by combining with the above items, 50-272/84-26-02, pending final approval of the proposed exemptio.0 Local Leak Rate Testing(LLRT)
The purpose of this inspection was to ascertain that the LLRT was con-ducted in compliance with the requirements and commitments referenced in the following sections 3.1 and 3.2, and that the test results met the acceptance criteria specified in *the station procedures and Appendix J, 10 CFR 5.1 References
10 CFR; Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors
Salem Unit 1 Technical Specifications Sections 3/4.6.1, Primary Containment
Salem Unit 2 Technical Specifications, Sections 3/4.6.1, Primary Containment
- Updated Final Safety Analysis Report (FSAR), Section 6.2, Con-tainment Systems
ANSI/ANS 56.8-1981, Containment Systems Leakage Testing Require-ments
USNRC I&E Information Notice No. 85-71; Containment Integrated Leak Rate Tests 3.2 Documents Reviewed
M9-IAP-1, Revision 3, Inservice Inspection Department Administrative Instructions
M9-IAP-2, Revision 2, Inservice Inspection Department ISI Program
M9-ILP-CT-3, Revision 0, Inservice Inspection Type B and Type C Leak Rate Testing, December 4, 1985; On-The-Spot Change (OTSC)
Nos. 1, 2, 3, and *
Containment Integrated Leak Rate Test, Unit 1, Summary Technical Report, November 8, 1984
Containment Integrated Leak Rate Test, Unit 2, Summary Technical Report, October 13, 1983
Licensee Event Report (LER), 83-010/03L, March 8, 1983, Containment Systems - Containment Types B and C Leak Rate -
Out-of-Specification 3.3 Test Results Evaluation The summary results and selected samples of Type B and C test results were reviewed and verified against 10 CFR 50, Appendix The Tech-nical Specifications, and NRC I&E Information Notice No. 85-7 The results are tabulated in the following table:
Unit Core v
VI VII Outage Date 1982/83 1984 1986 Sum of Types B & C, SCCM As Found As Left 57,917 59,154 27,461 29,033 16,203
- II III
1983 1984/85 45,756 Acceptance Criteria (0.6La):
129,750 SCCM 19,137 23,041 The above results met the acceptance criteria of 129,750 SCC The inspector also reviewed Deficiency Reports (DR) and associated Work Orders (WO), on a selected basis, to determine that the 11As Found 11 conditions were accounted for and that the 11As Left 11 and 11As Found 11 LLRTs were properly incorporated in the Type A, Containment Integrated Leak Rate Testing (CILRT) result, for 11As Found
correctio The DR 1 s and W0 1 s reviewed were:
Unit 2
DR# MT-84-121/WO #84-18-04-023-1; 22 CA 360 leaking for B Header Instrument Air
DR # MT-107; 22VC19 packing leaking
DR# MF84-106/DCR #84-10-04-027-1; 2VG-5 and 6 leak testing
DR# MT-84-105/WO #84-10-04-027-1; 2WL98 valve leaking
DR# MT-84-112/WO #84-10-04-027-1; 2NT34 valve leaking Unit 1
DR# MT 86-069/WO #85-09-04-003-1;
DR# MT 86-038/WO #85-09-14-003-1;
DR# MT 86-033/WO #85-09-14-003-1;
DR# MT 86-032/WO #85-09-14-003-1; lWR 81 1 PR17 13GB4 12GB4 valve leaking valve leaking valve leaking valve leaking The inspector discussed with the licensee representative the corrections made on the type A test results after repairs and and adjustment The inspector also discussed a correction to the 11As Left 11 type A test results and the intent of the NRC I&E Information Notice, No. 85-7 Subsequently, the licensee revised its procedures, M9-ILP-CT-1 and M9-ILP-CT-3, to reflect the I&E Information Notice No. 85-71.
- *
Based on these, the above open items were resolve The procedures now require the licensee to obtain both the 11As Found" and the 11As Left" LLRT data and derive a correction for the
"As Found 11 ILR The inspector also reviewed deviation (50-272/84-26-02) and questions (50-272/84-26-03, and 50-311/83-17-02) raised during previous inspection In response to the above findings the licensee took several correc-tive actions and submitted letters to NRR, dated November 5, 1984 and October 13, 1983, requesting several amendments and exemptions to the technical specification Based on the review of the above corrective actions and submittals to NRR, the inspector determined that items, (50-272/84-26-03, 50-272/84-26-02, and 50-311/83-17-02) would be resolved, pending final approval of the proposed changes by NR This is an unresolved item, pending NRR approval of the proposed changes (50-272/86-14-01, 50-311/86-13-01).
11As Found 11 CILRT Results The procedures M9-ILP-CT-3 and M9-ILP-CT-1 were reviewed to apply a correction factor to the type A test result as follows:
e The procedures require the licensee to obtain the 11As Found 11 and the "As Left" LLRT data
The 11As Found" ILRT can be calculated by adding an LLRT correction to the "As Left" ILRT as follows:
11As Found" ILRT= "As Left" ILRT
+ LLRT correction The LLRT correction is calculated as follows:
LLRT correction = Sum of
"As Found
LLRTs Sum of 11As Left
LLRTs e
The 11As Found 11 LLRTs were those obtained prior to the 11As Left 11 CILRT, and the 11As Left 11 LLRTs, immediately after the 11As Left 11 CILR Using the above, the inspector performed an independent calculation for the 11As Found" CILR The results are tabulated as follows:
Unit
2 The The LLRT CILRT Core As Found As Left Difference As Left As Found VI 59,154 29,033 30,121 ( O.139La)
( O. 411La) (0.55La)
III 45,756 19' 137 26,619 29,524 56,243 (0.123La)
(0.136La) (0.26La)
acceptance criteria for the results met the criterio Type A CILRT is 75% of 216,240 SCCM (0.75 La).
No unacceptable conditions were identifie Pl ant Tours The inspector made several inspection tours of the plant facilities, both units 1 and 2, including the Turbine Building Primary Auxiliary Building, and Control Roo The areas inspected included the following:
e EOG rooms Q
Auxiliary Feedwater pumps
Core Spray pumps
Volume Control Tanks
Control Room
Charging pumps
Component Cooling Water System Penetration
Containment Penetrations:
SA118 and CC225 The inspector observed operations and activities in progress, general condition of the safety-related equipment, component tagging, and system operation Findings At 1515 hour0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br />, April 30, 1986, the inspector observed a technician working on the #13 EOG air drye However, the technician did not have the Work Order (WO) which specified the repair work or procedures to guide the repair activitie The inspector raised a concern regarding the performance of maintenance activity on vital equipment without written guidance or work orde The work order #86-04-15-051-0 for the activities was later provide The inspector determined that this was an isolated cas However, probable safety-implications were discussed with
the technician and his management to prevent future recurrence The licensee stated that this particular activity did not require any written procedur On May 1, 1986, 0900 AM, the inspector noted an excessive water leak on 1WL13 near the SA11 The licensee was immediately notified and a work order #86-05-01-010-0 was issued for a repai.0 Unresolved Items Unresolved items are matters about which more information is required to as certain whether they are acceptable, or whether they are violations or deviation Paragraph 3.3 contains one unresolved ite.0 Exit Interview The inspector met with licensee management representatives (see Section 1.0 for attendees) on May 2, 198 The inspector summarized the scope and findings of the inspection at that tim At no time during the in-spection were written materials provided to the licensee by the inspectors.