IR 05000272/1993003
| ML18096B300 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 02/21/1993 |
| From: | Chaudhary S, Gray E, Kaplan H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18096B299 | List: |
| References | |
| 50-272-93-03, 50-272-93-3, 50-311-93-03, 50-311-93-3, 50-354-93-03, 50-354-93-3, NUDOCS 9303020296 | |
| Download: ML18096B300 (7) | |
Text
'**
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
REPORT/DOCKET NO /93-03 50-311/93-03 50-354/93-03 LICENSE NOS. *
LICENSEE:
- Public Service Electric & Gas Company 80 Park Plaz.a - 17C Newark, New Jersey FACILITY:
Salem Units 1&2 and Hope Creek Generating Station INSPECTION AT:
Hancocks Bridge, New Jersey INSPECTION DATES:
January 5-7, and January 19-22, 1993 INSPECTOR:
APPROVED BY:
. *~~~Reactor Engineer, Materials Section, EB, DRS
~*
s:Challdhary~~or Engineer Materials Section, EB, DRS
. Harold Gray, Chief, Engineering Branch, DR Date Date
- -1 ate Areas Inspected: Water chemistry~ service water systems, and snubber/pipe support
- progra Results: Review of reactor water chemistry results for the 1992-1993 period indicated*
conformance to Technic3.l Specification requirements. The recently installed Al-6XN stainless steel in service water systems is performing well. Additionally, the snubber/pipe
. program was found to be acceptable.
9303020296 930221 PDR ADOCK 05000272 G
".
2 WATER CHEMISTRY(Mod-84750). Scope This inspection covered a review of the 1992 chemistry results' for the reactor water systems (RCS) for both Salem (Units 1 and 2) and Hope Creek Statio. 2 Findings 1.2.1 Saleni Units 1 and 2
-
The data indicated that no deviations to the Technical Specifications were experienced during 1992.. All values were well below the specified limits for dissoJved oxygen($ 0.10 ppm),
chloride (:::;.15 ppm) and fluoride(~ 0.15 ppm). In addition, steam generator secondary side blowdown chemistry results conformed to station specifications for the same period. *A random check.of the daily chemistry records indicated that quality control samples were employed as required by specification SC.CH-TI.ZZ-0180(Q), Revision 2, and that analyses were performed in accordance with prescribed freq~encie.2.2. Hope Creek The data indicated that. no deviations to the Technical Specifications were experienced during 1992. All values were well below the specified limits for chlorides ($ 0.2 ppm) and
- conductivity ($ 1.00 µmhos/cm) and within the range for pH (5.6 - 8.6). A random check of the daily chemistry records indicated that quality control samples were employed as required by specification HC-CH-TI.ZZ-0012(Q), Revision 18, and that the analyses *were performed in accordance with prescribed frequencie The inspector also reviewed a QA surveillance report (92-43.5), dated 9/22/92, of the chemistry activities. No discrepancies in regard to procedure practices or technician qualifications were foun. 3 Conclusion Review of reactor water chemistry results for Salem and Hope Creek stations were found to conform to Technical Specification requirements.
3 SERVICE WATER SYSTEMS Scope This inspection covered a review of aspects of the service water systems for both Salem (Units 1 and 2) and Hope Creek stations, with special attention directed to the performance of the new Al-6XN stainless steel pipe. Approximately 85 % of the safety-related service water piping has been replaced with Al-6XN for Salem and 95 % for the Hope Creek stations. The installation for the Salem units was initiated in 1988, and for Hope Creek in *.
1991. Completion of the Al-6XN project is scheduled for the next outages (lRll and 2R7). Findings 2.2.1 Salem Since the installation of the Al-6XN material, the licensee has employed a comprehensive.
program to assure the integrity of the service water system, including inspection of piping, valves; pump and containment coolers*, strainers and other components. For the 1992 period, a total of 169 inspections for Unit 1 and 157 inspections for Unit 2 were completed and closed. On the basis of the results of the inspection program, the licensee stated that tlie new Al-6XN (6% Molybdenum) piping has performed exceedingly well, with only minor isolat~
pitting observed. In addition to the visual inspections, the licensee performed radiography on 3-inch fan cooler units (#11, #12, #14, #21, #22 and #23 in 1991 and 1992) and reported no evidence of corrosion in the weld joints. Additionally, the inspector reviewed a November 1990 report of Al-,6XN corrosion specimens removed from a test facility representing vaclous conditions (stagnant, flowing, ambient and heated - l10°F). The report indicated that the new material. was performing exceedingly*well as compared to type 316 companion stainless specimens, * which exhibited pronounced pitting and crevice attack. Prior to the 1990 inspection, examination intervals ranged from 30 days to 524 days. The next inspection is scheduled for the fall of 199 *. 2.2.2 Hope Creek The licensee continued to inspect various locations of the service water piping~ Except for several portions made from carbon steel which are to be replaced on the next outage (RS), no problems of degradation have been observe. 3 Conclusion The Salem and Hope Creek stations continue their Al-6XN replacement programs. The Al-6XN piping, which has been installeQ, is performing well.. The stations continue to maintain an active and viable inspection progra I
.
I
~.
- ,
4 PIPE SUPPORT AND SNUBBER INSPECTION Scope of the Inspection The scope of this inspection. was to determine, through direct observation and independent evaluation of licensee's program, whether the control system was functioning properly for installation, modifications, and/or maintenance of safety-related supports and restraints, and to determine that these supports and restraints* were in compliance with NRC requirements, licensee commitments, and applicable code The areas reviewed included:
. _ISI/IST program for snuqbers and other pipe supports (Program & Practices).
- Snubber maintenance shop and bench test program and procedures,
Visual examination of easily accessible snubbers; and
. *
General walk-through inspection of the plan.2. Findings 3.2.1 Program The snubber surveillance and maintenarice programs for both Units 1 and 2 at Salem Generating Station, are covered by a single program, and are controlled by the same requirements and procedures. The scope of the ISI/IST program is based on the Technical -
Specification requirements in this area and the Section XI of the ASME Code. The program is described in the Long-term Program Descriptions, Volumes 1 and Salem Unit 1 is in the second period of the second ten-year interval for the Code ISI program. Unit 2 is in the first period of the seeond interval of the Code ISI program. The ISI program for Unit 1 is in conformance to ASME,Section XI, 1983, with addenda through Summer 1983, and Unit 2 conforms to the 1986 Edition of the Cod The Program Plan is subject to revision due to plant modifications or changes in regulatory requirement *
Revisions to this program plan will be handled as follows:.
Minor changes (typographical errors, editorial changes, etc.) will be identified by marking up a copy of the affected pages in the Master Copy, making any necessary changes in the PC database program, "ISIC," and issuing the new revised sheet(s) through the Document Distributio Group (DDG).
Component selection-and scheduling changes will be tracked by marking up the Master Copy of the inspection plan during the scheduled outage. At the end of a Scheduled outage, the marked up plan will be reviewed and all required changes as well as all outage exam results, will be entered into "ISIC.,,. The revised Program Plan database portion of the manual will then be submitted for a controlled distribution through DD Major program plan changes (addition and deletion of components, relief requests, changes to Code requirements, etc.)
will all be tracke4 and maintained in a separate section within the manual. This section will receive a controlled distribution as the changes are made. Upon the completion of an inspection period, the entire manual will be revised to incorporate changes in this sectio The revised manual will receive the same review and approval process of the original manual and be distriputed to all controlled copy holders. In addition, major manual revisions will also be submitted to the NRC at the end of each perio The "ISIC... database will always be equivalent to the Master Copy and shall always reflect all program cqruiges, as they are made with the exception of component seleetion, and scheduling changes will be changed in the database at the end of the affected outag.2 Procedures By review of procedures applicable to the inspection and examination of snubbers and supports, the inspector determined that the procedures were technically good and were -
adequate in establishing procedural controls. The procedures were detailed and clearly written, with an adequate check list for inspection/examination, clearly established acceptance criteria, qualification_ of inspection personnel, and documentation of the results. The procedures meet the requirements of the ASME Code,Section XI. The inspector had no further questions in this area. -
~.
3.2.3 _Overhaul and Bench Test of Hydraulic Snubbers The inspector reviewed procedures applicable to the repair, overhaul, and testing of snubbers, and witnessed a snubber test in the repair sho The inspector noted that there were detailed pr()Cedures for accomplishing work in the following areas:
- *
,,
Mechanical Snubber ~em.ova.I and Installation,
Mechanical Snubber Testing,
. Hydraulic Snubber Performance Testing,
Hydraulic and Mechanical Snubber Functional Tests,
Snubber Service Life Monitoring,
Hydraulic and Mechanical Seismic Snubber Inspection, -
Snubber Inspection Failure Tracking, and
Hydraulic Snubber Overhau The inspector noted that the shop was well equipped for handling of snubber overhaul and tests, and well staffed by qualified personnel. :The inspector had no further questions in this *
'
'
.
are \\. *
3.3 Conclusions Based on the above findings, the inspector concluded that the snubber/pipe support -
inspection/surveillance program at Salem Generating Station, Units 1 and 2, was acceptable in its program scope and procedure implementatio.0 EXIT INTERVIEW At the conclusion of the inspections on January 5 and 22, 1993, the inspectors met with the licensee representatives, as indicated in Attachment 1; where the inspectors summarized the scope and the findmgs of the inspection '
.
~.
ATTACHMENT 1 Exit Meeting Attendees Public* Service Electric & Gas Company J. Barnes C. Conner R. Diaz J. Diericky K. Maz L. Miller J. Nichol L. Parri B. Rokes E. Villar C. Vondora
. System Engineering* - Salem Supervising Engmeer, ISI
.
Project Manager - Hope Creek
. Chemistry - Salem Chemistry.. - Hope Creek General Manager - Nuclear Operations Manager, Reliability & Assessment System Engineer - Hope Creek Licensing Engineer - Hope Creek.
Licensing Engineer General Manager - Salem U.S. Nuclear Regulatory Commission S.Barr T. Johnson H.J. Kaplan E. Wenzinger *
- Resident Inspector - Salem Sr. Resident Inspector Sr. Reactor Engineer Chief, Branch 2, DRP