IR 05000312/1986033

Insp Rept 50-312/86-33 on 860826-1010.No Violation or Deviation Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup Items

ML20213F542
Person / Time
Site:	Rancho Seco
Issue date:	10/30/1986
From:	Dangelo J, Miller L, Myers C, Perez G, Phelan P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20213F539	List: IR 05000312/1986033 ML20213F537
References
50-312-86-33, NUDOCS 8611140271
Download: ML20213F542 (9)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION V

Report No: 50-312/86-33 Docket N License No. DPR-54 Licensee: Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Facility Name: Rancho Seco Unit 1 Inspection at: Herald, California (Rancho Seco Site)

Inspection conducted- .

Inspectors: / b rl 10 M J A. OD' ngela, r* esident Inspector Date Signed b

C. J.J ers, Re'

I O - To -$lo Date Signed en,t nsppctor

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( 10-3046 G. P. Pere , Resident Ins c br Date Signed ( (JM ID- D 0(o P. Phelan,' egional ec.or Date Signed Approved by: 10 ' 30 -d b L. F. MijJer, Chief, Readtor ProjectsSection II Date Signed Summary:

Inspection between August 26 and October 10, 1986 (Report 50-312/86-33).

Areas Inspected: This routine inspection by the resident inspectors, by one regional inspector and one contractor, involved the areas of operational safety verification, maintenance, surveillance, meeting with local officials, and followup items. During this inspection, Inspection Procedures 30702, 30703, 61700, 61726, 62703, 71707, 90712, 92700, 92701, 92702, 93702, 94600 and 94702 were use The inspection involved 275 hours0.00318 days <br />0.0764 hours <br />4.546958e-4 weeks <br />1.046375e-4 months <br /> by three inspector Results: No violations or deviations were identifie PDR ADOCK 05000312 O PDR

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DETAILS Persons Contacted Licensee Personnel

• 1J. Ward, Deputy General Manager

{J.Vinquist,ExecutiveAssistant K. Perkins, Restart Implementation Manager

• G. Coward, Deputy Restart Implementation Manager

• J. McColligan, Assistant Manager, Nuclear Plant

• 1 0. Poole, Plant Manager R. Ashley, Licensing Manager D. Army, Nuclear Maintenance Manager B. Croley, Deputy Plant Manager D. Gillispie, Nuclear Engineering Manager S. Redeker, Nuclear Operations Manager J. Shetler, Deputy Implementation Manager T. Tucker, Nuclear Operations Superintendent M. Price, Nuclear Mechanical Maintenance Superintendent L. Fossom, I&C Maintenance Superintendent

• R. Colombo, Regulatory Compliance Superintendent J.' Field, Nuclear Technical Support Superintendent S. Crunk, Incident Analysis Group Supervisor J. Jurkovich, Site Resident Engineer 7F . Kellie, Radiation Protection Superintendent Stu Knight, Quality Assurance Manager

• T. Carver, Nuclear Licensing Supervisor

• T. Shewski, Quality Engineer

• D. Martin, Manager, Emergency Preparedness C. Stephenson, Regulatory Compliance Engineer C. Linkhart, Electrical Maintenance Superintendent Other licensee employees contacted included technicians, operators, mechanics, security and office personne { Attended the Exit Meetias on October 10, 198 Management Analysh, Csanpany (MAC) Personnel Operational Safety Verification The inspectors reviewed control room operations which included access control, staffing, observation of decay heat removal system alignment, system status and review of control room logs. Discussions with the Shift Supervisors and operators indicated understanding by these personnel of the reasons for annunciator indications, abnormal plant conditions and maintenance work in progress. The inspectors also verified, by observation of valve and switch position indications, that emergency systems were properly aligned for the cold shutdown condition of the facilit . . . _ ._ _

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Tours of the auxiliary building and turbine building including exterior areas, were made to assess equipment conditions and plant conditions.

, Also the tours were made to assess the effectiveness of radiological controls and adherence to regulatory requirements. The inspectors also

observed plant housekeeping and cleanliness, looked for potential fire and safety hazards, and observed security and safeguards practice On October 3, 1986, at approximately 9

47 a.m., decay heat removal was

. lost for 13 minutes. Prior to the-loss of cooling, decay heat removal loop B was in operation and loop A was not functional due to planned maintenance activity in process. The reactor coolant system was drained down to the hot legs. Loss of decay heat removal was caused by closure of an isolation block valve (HV-20002) on the decay heat removal pump suction. The valve closed due to a spurious signal recieved by emergency safety features actuation system (SFAS) analog channel B. The licensee is investigating the spurious signal and stated that a possible cause may be an electrical transient on 120 volt vital AC bus S1 Incore thermocouple readings remained stable at approximately 84 F during the period of no forced flow by the decay heat removal system. The plant has been in cold shutdown for 290 day The inspector will continue to monitor the licensee's investigatio The emergency preparedness _ aspects of this event including the need to declare an emergency action level will be discussed in inspection report number 50-312/86-32.

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No violations or deviations were identifie . Monthly Surveillance 1 Technical Specification (TS) required surveillance tests were observed and reviewed to ascertain that they were conducted in accordance with these requirement The following items were considered during this review: Testing was in accordance with adequate procedures; test instrumentation was calibrated; limiting conditions for operation were met; removal and restoration of the affected components was accomplished; test results confirmed with TS and procedure requirements and were reviewed by personnel other than the individual directing the test; the reactor operator, technician or engineer performing the test recorded the data and the data were in agreement with observations made by the inspector, and any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personne . Battery Surveillance

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The inspector reviewed the tests associated with the replacement of the A, C, and D safety related batterie The licensee had elected to replace the batteries after degradation was observed ir 'he cells, and concerns were raised as to the reliability and operability of the batteries. Before replacing the batteries, the

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licensee had performed a service test on two of the batteries and a capacity discharge test on the other. The "B" battery is scheduled to be tested r,nd replaced during the current outage. All test procedures reviewed appeared adequate and the test results were satisfactory. The licensee demonstrated that, even though individual cells of the batteries displayed visual evidence of degradation, the integrity of the battery, as a whole, was sufficient enough to serve its intended safety functio The licensee is revising its b r.tery surveillance procedures to assure that the recommendations of the manufacturer and IEEE 450-1980, " Maintenance, Testing and Replacement of Large Lead Storage Batteries", are fully incorporated into the procedure A review of the procedures under revision showed that these recommendations were being incorporate The inspector observed broken thermometers in the bottom of the cells' jars in the non-safety-related battery banks BJ and BK, and in the safety-related bank BA-2. The licensee contacted the manufacturer concerning this issue and was informed that the broken thermometers would not fail the battery. To preclude similar occurrences, cognizant personnel were instructed to exercise more care when working with and around the thermometers. The inspector found the licensee's actions adequate to resolve this concer Steam Generator Surveillance An NRC contractor reviewed the licensee's program for eddy current inspection of the once through steam generator (OTSG). The detailed

. results of his inspection is documented as Attachment 1 to this report. In summary the inspector found that personnel certifications were acceptable for those reviewed, verification and qualifications of the written procedures were acceptable, the eddy current techniques applied were acceptable, and the results of the OTSG's inspections were in compliance with the licensee's technical specification Routine Surveillances The following routine surveillances were observed and the results were reviewed:

SP 200.01 " Instrumentation Surveillence Performed Each Shift" SP 206.03A " Diesel Generator G-886A Synchronization Surveillance Test" SP 200.14 " Process Instrumentation Calibration Surveillance" No violations or deviations were identifie . Maintenance Maintenance activities for the systems and components listed below were observed and reviewed to ascertain that they were conducted in accordance

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with approved procedures, regulatory guides, industry codes or standards, and the Technical Specification The following items were considered during this review: The limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing or calibration was performed prior to returning components or systems for service; activities were accomplished by qualified personnel; radiological controls were implemented; and fire prevention controls were implemente Fire Barriers The inspector reviewed the licensee's fire protection (FP)

organization in the area of non-functional and breached fire barriers. Early in 1985, the licensee had upgraded its FP program including a revision of the FP surveillance procedures. The procedures had been reviewed to assure that acceptance criteria were consistent with license commitments and industrial standards. As a result of the licensee's review, the number of non-functional fire 'r doors, fire dampers, mechanical penetration seals and electrical L penetration seals identified increased to approximately two hundre The licensee is currently performing engineering evaluations on many barriers and is revising procedures to deal with the breached barriers in a more timely and efficient manner. The inspector found that the licensee actions appeared adequat Snubber Repairs The inspector observed repair work being performed on various hydraulic snubbers during this report period including radiological work practices. This work was being performed by a snubber vendor contractor, and monitored by a Quality Control inspector. The inspector concluded that the work observed appeared adequat No violations or deviations were identifie . Followup Items Open Items (CLOSED) Open Item 84-19-02: Overvoltage Check in NNI Surveillance Not Included in Procedur The licensee revised preventive maintenance (PM) tasks to calibrate and functionally test both the Integrated Control System and the Non Nuclear Instrumentation Systems. These PM tasks will, in part, verify the overvoltage protection setpoints for the NNI X, Y, and Z power supplies and the ICS power supplies. These PM tasks are to be performed on a refueling outage basis. The inspector verified that the PM tasks included the overvoltage setpoint check. This item is considered closed. (84-19-02, Closed.)

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5 Enforcement Items (CLOSED) Deviation 86-21-03, " Nuclear Service Raw Water System Not Being Maintained Per Commitments."

As stated in Inspection Report 86-21, the nuclear service raw water spray ponds' filters were found not operating on various days, and, therefore, not providing continuous cleaning of the water as committed in the Updated Safety Analysis Repor The licensee has issued c Special Order to the operations staff which required the filtration system to be operate 1 on a continuous basis. The licensee will also revise the operating procedure to reflect the' requirement for the continuous operation of the filtration syste In addition, the licensee performed a walkdown of the spray pond The licensee concluded that the nuclear service raw water system was operable per the Technical Specification The inspector concluded that the licensee's actions would, when completed, satisfy the USAR commitments which had been violated in this deviation. The inspector will continue to verify the licensee's corrective actions. This item is closed. (86-21-03; Cclosed.)

(CLOSED) Violation 86-21-05, " Auxiliary Feedwater Flow Indication in the Control Room."

As stated in inspection report 86-21, the licensee had failed to install class 1E auxiliary feedwater flow indication in the control roo This was a violation of an NRC Order which encompassed NUREG-0737. Item II.E. In the licensee's response, dated September 5, 1986, the licensee concurred with the violation. The licensee stated in their response that as part of.their efforts to install the emergency feedwater initiation and control system (EFIC) the auxiliary feedwater flow indicators will be upgraded to safety grade prior to the plant's restar The inspector found that the above actions would correct this violatio On the basis of this unambiguous recommitment by the licensee; this enforcement item is close (86-21-05: Closed.) Lit.ensee Event Report (LER) Followup

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The following LERs were reviewed for conformance with the 10 CFR 50.73 reporting requirements:

LER 85-14, Rev.1 "NSCW Pump "A" Class 1 Breaker replaced with

' Class 2" (OPEN)

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.LER 86-07, Rev.1 " Control Room HVAC High Flow Condition" (OPEN)

LER 86-11, Rev.0 " Voluntary Report on Loose Conductor / Lug Assemblies in Manufacturer Supplied Cabinets" (OPEN)

LER 86-12, Rev.0 " Control Room Emergency HVAC Spurious Actuation" (OPEN)

The reporting requirements appeared to be met. The licensee's followup actions addressed in these LERs will be reviewed during future inspections as necessar LER 86-18, Rev.0 " Compensatory Fire Protection Measures not Established" (CLOSED)

LER 86-18 was closed based on in-office review which included an evaluation by the inspector of compliance with 10 CFR 50.7 Also, the LER was evaluated to ensure compliance with fire protection program commitment . Meetings The inspector and members of the NRC Regional staff were asked to talk to the Sacramento Chamber of Commerce Task Force. The presentation involved a discussion of the role of the NRC and answering questions posed by the Task Force members on the NRC's activities at Rancho Sec Region V management met with the licensee to assess licensee progress on the Performance Improvement Program during the period September 22-26, 198 . Exit Meeting The resident inspectors met with licensee representatives (noted in Paragraph 1) at various times during the report period and formally on October 10, 1986. The scope and findings of the inspection activities described in this report were summarized at the meetin >

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ATTACHMENT 1

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The following are the results of an inspection conducted by an NRC contractor, Brozia H. Clark Jr. , that was documented in a letter dated August 24, 1986 from B. H. Clark Jr. to D. F. Kirsch NRC:

Subject: Review of the Nondestructive Testing Electromagnetic Eddy Current Testing System and Method Applied for Examining Tubular Material of Construction, Once Through Steam Generator (OTSG) "A" and "B", Rancho Seco, Nuclear Power Plant Station, Herald, CA, August 18 thru 20, 198 Review: Personnel Training

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Certification and qualification, nondestructive testing and training of personnel was established by Sacramento Municipal Utility District (SMUD)

and was in compliance with the written practice of Babcock and Wilcox's ISI-24, Rev.8, issued 8-6-81, revised 8-5-86. The written B&W procedure ISI-24 equates and exceeds the recommended training guidelines practices of SNT-TC-1A, Supplement "E" and the ASME Code Section XI, IWA-230 A total of seven personnel certifications were reviewed for Levels II, IIA, and II The personnel certifications were determined to be acceptabl . Verification and Qualification of the Written Procedure The electromagnetic eddy current written procedures, B&W's I51-418 and 425, which were applied for the examination of the tubular material of construction, "A" and "B" 0TSGs are in compliance with and exceed the requirements of Section V, Article 8 and Section XI, Appendix IV, minimum requirement Verification and qualification of the written procedures, 15I-418 and 425 were determined to be acceptabl The criteria for the acceptance and rejection of the tubular material was established using the multifrequency and multiparameter test data. In the multiparameter method, data from the individual frequencies are combined in real time by a vector addition process referred to as mixin This mixing process eliminates unwanted test parameters while retaining those of interes The eddy current method techniques applied were determined to be acceptabl Calibration of the system was established using a B&W Eddy Current Standard, Inconel 600 per Dwg. 1155026 B-1, Data Base #4911 of 2/28/8 _ _ _ _ _ _ _ _ _ _ . -

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. 8 SMUD Rancho Seco facilities employed contractual NDT Eddy Current personnel to perform the OTSG tube examination and analyze the dat This was performed by B&W and CoAm level IIA and III Data Analyst personnel. The data analyzed gave preference as to a tubes' remaining structural integrity and service life within the boundaries of the tube sheets and supports. The data evaluated was in accordance with B&Ws'

ISI-460, 462, and 463. Use of other B&Ws' ISI ET procedure techniques were available when neede Tube plugging was based upan an ET indication response which equated to or was greater than 40% tube wall loss. Other tube plugging having a response less that 40% of tube wall loss was based upon tube wall loss deterioration rates when compared with a previous examination. This plugging method was considered as a preventive maintenance measure. The result of the "A" and "B" sample inspection was in compliance with Rancho Seco Technical Specification Surveillance Standard 4.14, Steam Generators for the classified categories C-1, C-2 and C-3 inspection requirements, and for plugging per 4.17.4 Acceptance Criteri Tube plugging this examination period 8/15/86 OTSG unit "A" recommending 6 tubes of the 9% examine OTSG unit "B" recommending 4 tubes of the 6% examine . Equipment Verification - Qualification / Certification A review of Babcock and Wi'icox quality control inspection reports relating equipment qualification and certification for usage this period of examination of the review covered:

H.P. 9836 Computer MIZ-18, Remote Acquisition Unit, Soft Ware, and Eddy Current Bobbin Coil Probe The equipment was found to be acceptabl .

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