IR 05000272/1987029
| ML18093A533 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/14/1987 |
| From: | Strosnider J, Winters R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18093A532 | List: |
| References | |
| 50-272-87-29, NUDOCS 8712220046 | |
| Download: ML18093A533 (7) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report N /87-29 Docket N License N DPR-70 Licensee:
Public Service Electric and Gas Company 80 Park Park Plaza - 17C Newark, New Jersey 07101 Facility Name:
Salem Generating Station, Unit 1 Inspection At: Hancocks Bridge, New Jersey Inspection Dates:
October 26 - 30, 1987
Inspector:
R. W. Winters, Reactor Engineer, MPS, EB, DRS, Region I Approved by:
rev J. StrOSflide;::
ef, Materials & Processes Section, Engineering Branch, DRS, RI date date Inspection Summary: Routine unannounced inspection -on October 26 - 30, 1987 (Report No. 50-272/87-29)
Areas Inspected: Steam Generator Inservice Inspection and Open Items Results: No violations or deviations were identifie PDR ADOCK 05000272 Q
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DETAILS 1.0 Persons Contacted Public Service Electric and Gas Company K. Bar, System Analysis Group R. Brandt, Inspection Services Engineer J. Clancy, Principal Engineer, Radiation Protection R. Dolan, Chemistry Engineer L. Fry, Station Planning Manager R. Graybill, Manager Procurement W. Schultz, Manager, QA Programs and Audits G. Slaby, Sen.ior Nuclear Performance Supervisor R. Smith, Senior Staff Engineer, System Analysis Group W. Treston, Senior Engineer, Site Maintenance and ISI D. Vito, Senior Engineer Licensing
- J. Zupko, General Manager, Salem Operations United States Nuclear Regulatory Commission
- A. Finkel, Senior Reactor Engineer
- ~. Gibson, Resident Inspector
- T. Kenny, Senior Resident Inspector
- J. Prell, Reactor Engineer
- D. Silk, Operations Engineer
- Denotes those attending the exit meetin The inspector also contacted other administrative and technical personnel during the inspectio.0 Licensee's Actions on Previous NRC Concerns (Closed) Deviation (50-272/86-25-01 and 50-311/68-25-01)
Inadequate quality controls for the designation, purchase, receipt inspection, verification, and documentation of lubricants Neolube and Fel-Pro N500 The inspector determined that the lubricants Neolube and Fel-Pro N5000 had been added to the list of materials requiring certificatio Purchase orders, receiving inspection reports and certifications for these materials were reviewed and found satisfactor The stock of these lubricants in the maintenance storeroom was observed to have the appropriate Quality Control release tag * *
This deviation is close (Closed) Deviation (50-272/86-25-02 and 50-311/86-25-02)
Failure to_
address action item 4 of Bulletin 82-0 Failure to submit a written report following an outage when threaded fasten~rs were cleaned and inspected before reus The required report was sent to the NRC Region I office November 21, 1986 by licensee letter NLR-N8617 The inspector reviewed the report and determined it was satisfactor This deviation is close.0 References/Requirements Steam generator surveillance activities were inspected to determine compliance with the following documents:
1. Technical Specification - Steam Generators - paragraph 3/4... Updated Final Safety Analysis Report - Steam Generators -
paragraph 5..0 Activities Reviewed The inspector reviewed the eddy current test (ECT) data collected through the time of the inspection during the outage in progress, the water chemistry results from the time of plant startup, and the radiation records for the work done on steam generators during the outage in progres.1 Steam Generator Eddy Current Inspection Details of the Review No eddy current testing was in process during this inspectio However, the inspector reviewed the preliminary results with the 1 i censee* personne 1 and discussed the program that was being followe In addition to the inspections required by the technical specifications the licensee had performed a special inspection to determine the location of the antivibration bars in the U-bend section of the steam generator-.
Location of the antivibration bars is necessary as input to the licensee's evaluation of the steam generator tube susceptibility to the fatigue cracking mode of tube failure that occurred at North Ann Findings Preliminary ECT inspection results were available for revie These data were generated by the computer printou~ made during the testing and had not been reviewed for adequacy or accurac Based on these data the licensee had identified two tubes as defective, analyzed these results and plugged the A third tube that had been previously plugged with a explosively expanded plug was identified as have a leaking plu A procedure for welding repair of this leaking plug was being develope A total of 1152 tubes were inspected full length (tubesheet to tubesheet).
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tubes were inspected to the top of the tubeshee In addition all tubes in rows 8 through 12 were inspected to verify the location of the antivibration bar The preliminary data indicated that 931 tubes exhibited some degree of denting at the top sides of the support plate on the hot leg side and one tube dented at both the hot and cold top support plat Conclusions Eddy current testing adequately met the requirements of the technical specification In addition the licensee performed an inspection to locate the antivibration bars in steam generator number 1 No deviations or violations were observe.2 Water Chemistry Details of the Review The inspector reviewed the water chemistry history for the past ten years that had been developed in response to an NRC letter requesting information as a result of the Surry pipe erosion/corrosion incident in December 198 Also reviewed were weekly plots of iron and copper.
It should be noted that oxygen, pH, and hydrazine are recorded continuously while the plant is in operatio In addition the plant chemist maintains plots of water chemistry with notations of power transient These plots indicate that any power transient will effect water chemistr However, the data was not conclusive because of the few transients experience Findings The inspector reviewed past water chemistry data and concluded that the licensee has been following the.Electric Power Research Institute (EPRI) guidelines as a minimum and has maintained excellent control during the lifetime of the plan This is reflected in the very small number of tubes plugged (16) in the number 13 steam generato Table I shows the maximum and m1n1mum values for tests made of the water in the secondary water syste From these data and a review of the weekly report of iron and copper results it was determined that the times when water chemistry was out of the tolerances provided by the steam generator manufacturer was during transients caused by power change The data furnished did not show any anomalies for chlorides indicating that there were no condenser tube failures during the past year where the brackish water from the Delaware River gained entry into the secondary system..
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Conclusions Except for periods of transient operations the inspector did not observe any periods where the water chemistry was in violation of the steam generator manufacturers recommendation No deviations or violations were observe.3 Radiation Exposure Details of the Review Radiation exposures are tracked by work order number and activity within the work orde For the number 13 steam generator the work order had 17 activities to be performe Each of these activities had estimated man-rem and actual man-rem information entered dail The actual work orders were reviewed by the inspector as well as a the summary of exposures incurred through October 26, 198 This method of tracking allows the licensee to closely estimate exposures and with the daily entries quickly observe deviations from the estimates and take prompt corrective action if required to reduce exposure Findings Radiation exposure is closely tracked, planning and scheduling is done to try to avoid the need to install dams in the main water lines*
from the reacto During the outage installation of these dams was unavoidable and it accounted for approximately 55% of the exposure received to dat Helium leak detection operations to determine the location of the leaking plug accounted for another 9% of the exposur Actual eddy current inspection is done remotely once the equipment is installed and results in exposure only when probes are changed'or other maintenance activities are require Conclusions The licensee was attempting to maintain exposures for the steam generator inspection and repair project as low as reasonably achievable through the use of remote inspection equipment, good controls of the inspection process, and close monitoring of the exposure records generate No deviations or violations were observe.0 Management Meetings Licensee management was informed of the scope and purpose of the inspection at the entrance interview on October 26, 198 The findings of the inspection were discussed with licensee representatives during the course of the inspection and presented to licensee management at the October 30, 1987 exit interview (see paragraph 1 for attendees).
At no time during the inspection was written material provided to the licensee by the inspecto The licensee did not indicate that proprietary information was involved within the scope of this inspectio r-
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TABLE I STEAM GENERATOR MANUFACTURERS RECOMMENDATIONS Control Parameters
Cation Conductivity Due to Strong Acid Anions at 25°C, uS/cm
Total Cation Conductivity at 25°C, uS/cm
Dissolved Oxygen, ppb (a)
Diagnostic Parameters
Total Organic Carbon, ppb
Sodium, ppb Ferrous Systems (b)
pH at 25°C
Specific Conductivity at 25°C,uS/cm
Ammonia, ppb Ferrous/Copper Systems (b)
pH at 25°C
Specific Conductivity at 25°C, uS/cm
Ammonia, ppb *
< 0.15
< < I 10
< 100
<< 1 9.3 -.2 - 1 ;8 -.8 - SALEM RESULTS SAMPLING POINT
- Steam Condensate Generator Pump Discharge pH 9.2/.4/ Total Cond (umhos/cm)
2.21/0.79 5.35/2.11 Cation Cond (umhos/cm)
.192/.055
.145/.06 Dissolved. Oxygen (ppb)
150/1 Sodium (ppb)
4.4/ /<5 Silica (ppb)
77/5 Iron (ppb)
670/<1 Copper (ppb)
260/<1 Sulfates (ppb)
3.3/<.2 Chlorides (ppb)
1.8/<.1
<50/<50 Ammonia (ppb)
185/78 Hydrazine (ppb)
87/<10 Maximum/Minimum values shown Make Up Steam Water 8.5/.5/8/8 5.34/0.08 NR /.06 1000/50 5/5 1. 6/0.5
<5/<5 9/<5
<1/<1 12/<1 6.8/.4/< <50/<50 Feedwater 9.4/. 54/1. 62
.110/. 055 15/.6/< /1 16/<l 3.6/<.l 0.2/< /150 141/<10