IR 05000261/1979017
| ML14175B089 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 08/29/1979 |
| From: | Kellogg P, Mchenry T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML14175B088 | List: |
| References | |
| 50-261-79-17, NUDOCS 7910190045 | |
| Download: ML14175B089 (10) | |
Text
d~oi REG,
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION Il 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report No. 50-261/79-17 Licensee:
Carolina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 Facility Name: Robinson 2 Docket No. 50-261 License No. DPR-23 Inspection at Robinson Site, Hartsville, South Carolina Inspected by:
T. J. Mc enry
/Da e Signed Approved by:
_
P. J. Rellogg, Section C ief, RONS Branch Date Signed SUMMARY Inspected on August 7-10, 1979 Areas Inspected This routine, unannounced inspection involved 31 inspector-hours onsite in the areas of post refueling restoration; refueling maintenance; IE Notice, Circular and Bulletin followup; licensee event followup; open item review and independent inspection effor Results Of the 6 areas inspected, no apparent items of noncompliance or deviations were identifie O0$?
DETAILS Persons Contacted Licensee Employees R. B. Starkey, Jr., Plant Manager
- C. W. Crawford, Operations Supervisor H. S. Zimmerman, Maintenance Supervisor
- J. M. Curley, Engineering Supervisor
- B. W. Garrison, Quality Assurance Supervisor C. Wright, Engineering Technican
- M. Page, Engineer R. S. McGirt, Senior Nuclear General Specialist W. T. Traylor, Administrative Supervisor Other licensee employees contacted included technicans, operators, and office personne *Attended exit interview 2. Exit Interview The inspection scope and findings were summarized on August 10, 1979, with those persons indicated in Paragraph 1 above. The inspection activities presented in these details were discusse.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspectio.
Post Refueling Restoration The inspector reviewed facility records to assure that safety-related systems disturbed during the refueling were returned to service in accordance with approved procedure Specifically, the following system alignment check off sheets were verified completed prior to startup and were reviewed to insure system alignment as specified:
OP-3B, Plant Electrical Distribution OP-6A, Service Water System OP-14A, Auxiliary Feedwater System
-2 OP-25A, Reactor Coolant System OP-40A, Component Cooling System OP-42A, Safety Injection and Containment Spray Systems Plant startup records consisting of Operator logs, Shift Foreman logs and completed startup procedures were also reviewed to assure plant startup was conducted as required by Technical Specifications and administrative policie The inspector also reviewed completed procedures and logs to assure that Technical Specification requirements were satisfied during the refueling outag The following Periodic Tests (PT's) were reviewe PT-1.0, Overall Refueling Interval Test Procedure PT-1.1, Source, Intermediate and Power Range Weekly (While Reactor Shutdown)
PT-1.6, Nuclear Instrument Audio Count Rate Channel Weekly (While Reactor Shutdown)
No problems were identified with regard to surveillance testing during refueling or system restoration prior to plant startu.
Refueling Maintenance The inspector reviewed completed maintenance packages for selected mainten ance activities conducted during the refueling outag Maintenance activities were reviewed to verify that administrative require ments were implemented in the following areas:
a. Administrative approval for system removal from and return to servic QA approval and revie Use of special requirements such as open flame permit, fire watch, radiation work permit and system clearanc Control of cleanliness, jumpers and housekeeping Provisions for assuring systems valves and breakers were aligned for normal operatio Provisions for assuring that redundant equipment was verified operable prior to maintenance and affected equipment was tested prior to restoring to operable statu Within the areas of inspection no problems were identifie.
Review of Licensee Event Report (LER's)
The inspector reviewed thirteen LER's for consistency with the requirements of Technical Specification, section The licensee analysis of the event, corrective action taken was reviewed and discussed with licensee representatives. The following LER's were discussed, reviewed and closed by the inspector: LER 79-05, Boric Acid Transfer Pump Broken Shaft The licensee had experienced a history of shaft failures on this type of pump (Chempump Model GE-20K) and had made tentative plans to replace the pump during the refueling outag The inspector discussed this item with operations personnel and determined that the pump had been replaced as planned during the refueling outage. The replacement pump (Model GVH-10K) had also been used to replace the redundant boric acid pump and had proven reliable in two years of servic LER 79-06, Boric Acid Transfer Pump Broken Shaft In addition to discussion in paragraph 7.a, the inspector reviewed plant logs to assure that the boric acid transfer pump was restored to operable status within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period allowed by Technical Specifi cation 3.2.3.b. Plant Logs indicated that the pump was inoperable for approximately 9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> The inspector discussed deficiencies in this LER with plant personnel responsible for LER review in order to correct deficiencies in subsequent LER' The following LER discrepancies were discussed:
1)
This LER is in effect reporting two events of the same type which occured in a very close time perio The cause description section does not clearly indicate that the boric acid transfer pump was declared inoperable following the first failur Inspector review of logs and records indicates that the pump was actually declared inoperable. This LER should have clearly indicated that the pump was declared inoperable for both period )
The cause and description section does not state the time that the boric acid transfer pump was restored to operable statu The inspector stated that the duration of inoperability should be indicated on LER in order to indicate the status of compliance with limiting conditions for Operations required by Technical Specification The inspector noted that the above concerns were not generic to most LER's but efforts should be made to correct these isolated discrepancie Licensee representatives acknowledged the inspectors comments and stated that more attention would be given to future LER's in the areas of concer LER 79-07 Primary to Secondary Leakage The inspector reviewed plant logs to verify that unit was in cold shutdown within thirty hours as required by Technical Specification 3.1. The inspector also discussed current status of steam generator leakage with operating personne Current leakage was less than measurabl LER 79-08 Safety Injection Pump Failed to Start The inspector determined that this item was incorrectly reported as being contrary to the surveillance requirements established by section 4 of the Technical Specification This LER was discussed with a licensee representative responsible for LER revie The inspector stated that section 4 of the Technical Specification is in general provided to demonstrate the operability requirement for the Specifi cation and Limiting Conditions of section Therefore, failure of a surveillance test constitutes inoperablity of equipment and should be reported in section 3 of the Technical Specification The inspector also stated that failure of equipment during surveillance testing when plant conditions do not require equipment to be operable should be reported as inoperable equipment which would have constituted a limiting condition for operation. However, an LER is not required if it can be determined that equipment failure did not exist when plant conditions required equipment to be operabl Licensee representatives acknowledged the inspectors comments and stated that future LER's would be reviewed with regard to the inspectors comment LER 79-09, Excessive Diesel-Generator Loading Time The inspector reviewed the Plant Nuclear Safety Committee (PNSC)
minutes and verified that this LER had been reviewe This LER was also identified as having been incorrectly reported and the inspector comments were the same as in paragraph LER 79-10, Engine Driven Fire Pump Inoperable The inspector discussed corrective action to prevent recurrence with the maintenance supervisor to determine what method was employed to emphasize "post weld" cleanu It was determined that this LER had been discussed and reviewed by appropriate personne At the exit interview the inspector discussed the LER format for stating corrective action involving instruction or review of event with plant personnel to prevent recurrenc The inspector stated that LER's should be specific as to what type of instruction or review will be or has been conducte Since the spectrum of instruction can vary from a review of the LER to formal class training, LER's should be specific in order to assess the adequacy of the corrective actio Licensee representatives acknowledged the inspectors comments and stated that information in the area of concern would be more specific in the futur LER 79-14, Source Range Channel Inoperable The inspector verified that operations personnel had reviewed this item as stated in the corrective actio The inspector offered the same comment as 7.f with regard to specific corrective actio LER 79-15 Purge Valve Excessive Leakage A similiar event was reported in LER 79-01 and was closed in inspector report 50-261/79-04. During the inspection of LER 79-01 the inspector stated that a review of reporatability associated with PPS leakage would be conducte With regard to reportability of Penetration Pressurization System (PPS)
leakage, the inspector stated that since there was no Technical Specification (TS) Limiting Condition for opera tion for the PPS, the fact that the narrow range PPS leakage was off-scale need not be reported. However, if it is determined that a containment integrity leakage limit required by TS section 4.4 has been exceeded, then a prompt report by TS section 6.9.2.a.3 is require Licensee representatives stated that future LER's with regard to PPS leakage would be evaluated for reporability as specified by the inspecto LER 79-16, Failed Interlock on Containment Hatch The inspector reviewed the license's actions with regard to the LER which was closed without commen j. LER 79-17, Primary to Secondary Leakage The inspector dicussed this LER with a licensee representative to deter mine the status of plugged tubes in all steam generators. Licensee's records indicate which tubes are plugged and that approximately three percent of the steam generator tubes were plugge LER 79-18, Auxiliary Feedwater Pump Inoperable The inspector had discussed this LER with a licensee representative on July 11, 1979 in order to determine what actions had been taken by the licensee to insure that this failure was not generic to the redundant pump. It was determined that the licensee had evaluated motor amps to insure satisfactory condition of the redundant pump moto The inspector reviewed plant logs and verified that plant cooldown to less than 350 degrees Fahrenheit was conducted in accordance with Technical Specifi cation section 3. This LER was discussed at the Exit meetin The inspector stated that the licensee's corrective action with regard to the redundant pump appeared adequate. However, there seems to exist a possibility of uncertainty. The inspector recommended that based upon this possible uncertainly, the licensee should consider an inspection of the redundant pump motor during a future outag Licensee representatives acknowledged the inspectors comments but made no commitment with regard to this ite.
LER 79-19, Nonconservative Safety Analysis The inspector verified that the Plant Operating Manual, and calibration procedures require the steam generator setpoint at 15 percen LER 79-20, Engine-Driven Fire Pump Inoperable A similar occurence had been reported in LER 79-1 The inspector discussed the licensee's tentative corrective action to install a filter in the fuel line with a licensee representativ It was deter mined that a design modification is being submitted to provide corrective action in regard to this ite.
Review of IE Bulletins (IEB's) IEB 79-09, Failure of GE Type AK-2 Breakers The licensee's response to IEB 79-09 indicated that there were no GE Type AK-2 breakers used or planned for use at the facilit The inspector discussed this item with the plant engineer who conducted the research for the matte No problems were identified and IEB 79-09 is close IEB 79-11, Faulty Overcurrent Trip Devices The licensee's response to IEB 79-11 indicated that no problems of the type described by the IEB were identifie However, three breaker of twenty four were identified with improper time delays due to worn 0-ring The licensee plans to institute a periodic test program for safety related breaker in order to detect future problem The inspector had no further questions with regard to this IEB which is close.
Review of IE Circulars and Notices (IEC's and IEN's)
The inspector verified that IE Circulars and Notices had been received onsite and reviewed by cognizant licensee personne Selected applicable IE Circulars and Notices were discussed with licensee personnel to ascer tain the licensees actions on these item The inspector also verified that IE Circulars and Notices were reviewed by the Plant Nuclear Safety Committee in accordance with facility administrative polic Licensee action on the following IE Circulars and Notices were reviewed by the inspector and are close IE Circulars IE Notices 79-01 79-02*
79-11 79-03*
79-05 79-12 79-04 79-06 79-13*
79-05 79-07 79-14*
79-06*
79-08 79-16*
-7 IE Circulars IE Notices (Continued)
79-07*
79-09 79-18 79-08*
79-10*
79-19 79-11*
- Indicates IEC's or IEN's not applicable to facility closed for record purpose onl. Review of Outstanding Open and Unresolved Items The inspector reviewed the licensee actions with regard to the following outstanding open and unresolved items: Open Item 79-09-02, Battery Low Voltage Alarm The inspector reviewed Trouble Ticket Number 994 completed on June 14, 1979 to verify that battery low voltage alarms had been calibrated as required. The inspector discussed this item with the plant engineer responsible for battery testing who stated that a annual battery low voltage alarm calibration had been incorporated into the preventative maintenance progra This item is close Open Item 79-03-02, Incorrect Valve Numbers on Q-List Drawing The inspector determined that the correct valve number had been incor porated into the new system drawin However, since the drawing had not been approved and issued for use this item will remain ope Open Item 79-11-02, 300 gpm Auxiliary Feedwater Flow The inspector reviewed the licensee's test results and procedure revisions with regard to this ite Tests and procedure changes indicated that the licensee's commitment to assure 300 gpm from each motor driven auxiliary feedwater pump prior to startup had been satis fie This item is close Open Item 79-12-05, Two Year Recertification of Inspectors The inspector verified that QAP-3A, Indoctrination and Training of Surveillance Personnel had been revised to require a 2 year requali fication as required by ANSI-N45.2.6-197 This item is close Open Item 78-04-03, Use of IVSW For Local Leak Testing The licensee had submitted a formal request to NRR licensing for a review of the IVSW system in regard to the plant safety analysis. In a letter to the licensee from NRR, Division of Operating Reactors dated April 23, 1979, it was concluded that the proposed IVSW system is acceptable for the performance of future Type C testing. This item is close Unresolved Item 79-11-07, Service Water Valve Omitted from Valve Checklist The inspector verified that at valve SW-564 had been added to check list OP-6A. In addition, the inspector reviewed service water modifi cations and drawing revision to ascertain if SW-564 had been omitted from OP-6A checklist as a result of a system modificatio This review indicated that valve SW-564 was added between 1968 and 1973 with no valve number assigne Due to the time period of valve addition and the extensive research that would be required to pursue this matter, this item did not appear to have sufficient safety significance, for further pursuit. This item is close Open Item 79-11-05, Fire Retardant Residue on Instrument Cabinet An inspection of various instrumentation cabinets and relay racks wa conducted to insure that fire retardant residue had been removed as required. All cabinets and relay racks were very clean. This item is close Unresolved Item 78-12-01, Establishment of Periodic Test Program for Circuit Breakers The licensee plans to establish a routine program for testing circuit breakers as described in paragraph This item is close Unresolved Item 78-06-01, Procedure to Reflect Modification of Reactor Building Crane This item was cited as item of noncompliance identified as item 78-15 01 which was closed in inspection 79-0 This item is close. Administrative Controls for General Procedure (GP) Implementation During the review of GP's utilized for plant heatup, power operation and cooldown the inspector noted that some steps had been marked as not appli cable in the sign-off blan In addition, discussion with operating personnel indicated that many steps in GP's are not required to be performed in chronological order. The inspector discussed this item with the Operations Supervisor. The inspector stated that the licensee needed to establish administrative procedural controls for GP's to govern the deletion of steps and the performance of steps out of delineated sequenc This item was discussed at the exit meetin The licensee acknowledged the inspectors comment and stated that action would be taken in regard to this matte The inspector identified this item as open pending a review of licensee actions during a future inspection (79-17-01).
1 Facility Tours The inspector toured portions of the facility including the auxiliary building, turbine area and control roo Particular attention was directed toward insuring newly installed fire doors were maintained closed and control room
-9 licensed maning requirements were satisified. Control room operations were observed and and discussed with control room personnel to assure compliance with Technical Specification No problems were identified.