IR 05000155/1988020

Insp Rept 50-155/88-20 on 880906-1017.No Significant Safety Items Noted.Major Areas Inspected:Surveillances of Reactor Depressurization Sys,Steam Drum Relief Valve Monitor,Station Batteries,Reactor Protection Sys & Bypass Valve

ML20205M549
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	10/24/1988
From:	Jackiw I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20205M540	List: IR 05000155/1988020 ML20205M535
References
50-155-88-20, NUDOCS 8811030143
Download: ML20205M549 (5)

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U.S. NUCLEAR REGULATORY COMMISSION

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REGION III

Report No. 50-155/88020(DRP)

Docket No. 50-155 License No. OPR-6 Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name: Big Rock Point Nuclear Plant Inspection At: Charlevoix, MI 49720 Inspection Conducted: September 6 through October 17, 1988 Inspectors: E. Plettner N. Williamsen Approved By: w tef, bI* M or Pro ects Section 28 Date I_nspection Sumary Inspection on September 6 through October 17, 1988 (Report No. 50-155/88020(DRP))

Areas Inspected: The inspection was routine, unannounced, and conducted by the Senior Resident Inspector and the Resident Inspector. The functional areas inspected consisted of the following: surveillances of the reactor depressurization system, the steam drum relief valve monitor, station batteries, reactor protection system, and the bypass valve; maintenance activities on various components including a depressurization system valve, a control rod drive hydraulic pump, a steam shaf t-seal on the main turbine, recalibration of the in-core detectors, and a control rod drive selector valve; operational safety verification of the liquid poison system, the reactor depressurization system, and power operations related to unidentified leak rate problems; and an engineered safety feature system walkdown of the post incident syste Results: The licensee has demonstrated a desire to respond in a timely manner to issues and concerns presented to them by the NRC. The surveillance, maintenance, and operational safety programs appeared to be performed in a manner to ensure public health and safety. No significant safety items were identified in this repor PDR ADOCK 05000155 0 PNU

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DETAILS

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1* N rsons Contacted

• T. Elward, Plant Manager

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• L. Monshor, Quality Assurance Superintendent

• H. Hoffman, Maintenance Superintendent

• R. Garrett, Chemistry / Health Physics Supervisor

• W. Trubilowicz, Operations Supervisor

• G. Withrow, Plant Engineering Supervisor R. Alexander Technical Engineer

• E. Zienert, Director Human Resources

• P. Donnelly, Nuclear Assurance Administrator

• R. Buckner, Nuclear Training Administrator The inspectors also contacted other licensee personnel in the Operations, Maintenance, Engineering, Radiation Protection, and Technical Department * Denotes those present at exit intervie .- Monthly Surveillance Observation (61726)

Station surveillance activities listed below were observed to verify that the activities were conducted in accordance with the Technical Specifications and surveillance procedures. The applicable procedores were reviewed for adequacy, test and process instrumentation was verified to be in their current cycle of calibration, personnel performing the tests appeared to be qualified, and test data was reviewed for accuracy and completeness. The NRC inspectors ascertained that any deficiencies identified were reviewed and resolved. The NRC inspectors observed the licensee's perfcrmance of the following surveillance tests on the indicated dates:

September 22,1988, T90-07, "Reactor Depressurization System Isolation l Valve Test" Rev. 30, dated April 28, 198 September 22,1988, T30-43, "Steam Drum Relief Valve Monitor Checkout",

Rev. 3 dated September 22, 1987.

! September 27,1988, T7-24. "Battery Pilot Cell Readings", Rev. 9, dated August 23, 198 September 27,1988, T30-20, "Battery Voltage and Specific Gravity (Station Battery #1, Station Battery #2, Alternate Shutdown System Battery, Uninterruptible Power Supply Batteries, Reactor Depressurization System Batteries)", Rev. 19 dated April 23, 198 October 4,1988, T7-04, "Weekly Reactor Protection Logic System Test", Rev. 10, dated Septerber 30, 198 .-_ __ . _ _ _ _ _ _ .

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October 4,1988, T30-01, "Monthly Reactor Protection System Test at i Power", Rev. 12, dated May 31, 198 '

October 4, 1988, T7-18, "Bypass Valve Test", Rev.10, dated May 18, 198 No violations or deviations were identified in this are I 5. Monthly Maintenance Observatio;. (62703)  ;

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Station maintenance activittes of safety related systems and components t listed below were observed / reviewed to ascertain that they were conducted ;

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in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with Technical Specification .I s i The following items were considered during this review: the limiting

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, conditions for operation were met while components or systems were removed .

from service; approvals were obtained prior to initiating the work; P activities were accomplished using approved procedures and were inspected *

i as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records t were maintained; activities were accomplished by qualified personnel; parts and materials used were certified; radiological and fire prevention controls were implemented.

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l Work requests were reviewed to determine status of outstanding jobs and to ;

assure that priority was assigned to safety related equipinent maintenance l which may affect system performanc i

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i The NRC inspectors observed the licensee's performance of the  !

1 following maintenance work orders on the indicated dates- .

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September 28, 1988, No. 88-M8E-0230, dated September 22, 1988, to i prepare samples from a Reactor Depressurization ,

System valve for shipment to a consultant laboratory i for analysi l

j September 28, 1988, No. 88-CRD-0284, dated August 15, 1988, to l replace the neoprene sleeve and the mandrel in ;

Control Rod Drive hydraulic pump (P4A) de-surge l

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i j October 4,1988, No. 88-TGS0100, dated July 26, 1988, to repair a -

J small steam leak at the No. I bearing on the main "

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turbin [

October 11, 1988, No. 88-NMS-0097, dated October 10, 1988, to i reculibrate the in-core flux monitor }

October 10, 1988, No. 88-CRD-0294, dated August 15, 1988, to t parform a preventive maintenance inspection on l Control Rod Drive selector valve C ; ,!

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October 10, 1988, No. 88-CRD-0315, dated September 1, 1988, to

. correct a small air leak in the connection on Control Rod Drive selector valve C No violations or deviations were identified in this are . Operational Safety Verification (71707)

The NRC inspectors observed control room operations, reviewed applicable logs, and conducted discussions with control room operators during the inspection period. Instrumentation and recorder traces were examinad for abnormalities and discussed with the control room operators, as were the

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status of control room annunciators. Reviews were conducted to confirm that the required leak rate calculations were performed and within Technical Specification limit System Walkdowns were performed to verify the operability of the liquid poison system and the Reactor Depressurization system. Tours of the containment sphere and turbine building were conducted to observe plant equipment conditions, including i potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance. Radiation protection controls were inspected, including Radiation Work Permits, calibration of radiation detectors, and proper posting and observance of radiation and/or contaminated areas. Security measures were inspected including access cont N1 of personnel and vehicles, proper display of identification badges for personnel within the protected area, and compensatory measures when security equipment had a failure or impainnen The NRC inspector accompanied an Auxiliary Operator on his tour to observe him in the performance of his duties. He appeared knowledgeable and competen During the week of October 9, 1988, an upward trend in the unidentified leak rate was observed ir the reacto'/ system. No leaks had been found in the normally accessible portions or the plant. When the unidentified leak rate passed the half-way point, relative to the Technical Specifications limit, the licensee made a & cision to reduce power and inspect for leaks inside the shielded enclosure which houses the steam drum and the recirculation pumps. On October 15 reactor power was reduced to allow for entry into the enclosure. A team of four men, comprised of a Senior Reactor Operator, an auxiliary operator, a health-physics technician, and the Resident Inspector, entered observing radiological-safety procedure The licensee found a steam leak from a bolted flange that connected the safety relief valve to the steam drum. Because of the low leak rate and location of the leak, the licensee decided to return to full power operation and develop possible methods to repair the leak. The power ascension procedure was started and later stopped when a malfunction of the control rod system resulted in two control rods being inserted out-of-sequence. In accordance with the Big Rock Point Plant Technical Specifications and Procedure ONP-2.7, "Mispositioned Control Rods", Re , dated May 18, 1988, the malfunction was diagnosed to be the master control valves. A set of four valves which govern the insert and withdraw timing sequence for all the control rods. The licensee changed

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to trie alternate set of master control valves to correct the malfunction.

l The out-of-sequence control rods were returned to the specified control i

rod pattern and a normal power ascension was continued with the plant achieving full power on October 1 No violations or deviations were identified in this are . Engineered Safety Feature System Walkdown (71710)

l The NRC inspectors the perfomed the Engineered Safety Feature (ESF)

i walkdown of the Post Incident System (the recirculation core spray system). The walkdown was performed on the accessible portions of the

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system. Included were verification of valve labels, equipment condition, correct valve and breaker positions and apparent operability of support l systems essential to the ESF system. A detailed review was conducted to l confirm that the licensee's system lineup procedure matched the applicable

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as-built drawings this included the following documents:

Procedure 0-TCS-1-A-8, "Post Incident System Check-Off List",

Rev. 36, dated October 2,198 *

Orawing No. 0740G44008, "Post Incident System Valve Lineup Diagram" Rev. 8, dated December 8,198 *

Orawing No. 0740G40123, Sheet 2, "Piping and Instrument Diagram, Post Accident System", Rev. G, dated December 18, 198 The walkdown and review revealed no significant problems that would preclude the system perfoming its intended safety function. Minor

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deficiencies were identified to the licensee for corrective actio No violation or deviations were identified in this are . Exit Interview

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The inspectors met with licenste representatives (denoted in Paragraph 1)

throughout the month and at the conclusion of the inspection period and surmiarized the scope and findings of the inspection activities. The licensee acknowledged these firdings. The inspectors also discussed the likely infomational content of the inspection report with regard to documents or processes reviewer. by the inspectors during the inspectio The licensee did not identify .iny such documents or processes as proprietar