RNP-RA/13-0079, Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter

Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter

ML13246A074
Person / Time
Site:	Robinson
Issue date:	08/21/2013
From:	Wheeler-Peavyhouse S Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/13-0079
Download: ML13246A074 (3)

Text

it AL c LM

""W- &V wvt" (DUJKE j MOM : V, M"=

F: so3W 131 Serial: RNP-RW1I3-(079 10 CFR 50.36 AUG`2- 12013 United States Nuclear Regulatory Commission Attn: Document Control Desk Washikngton, ' 20565 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEW.ED LICENSE NO. DPR-23 TECHNICAL SPECIFICATIONS (TS) SECTION 5.8.6, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION REPORT, 14-DAY REPORT FOR THE INOPERABILITY OF THE WIDE RANGE CONAINMEN Pe8 SURE TRNSMITR Ladles and Gentlemen:

Duke Energy Progress, Inc., kfomy known as Carolina Power and Light Company, Inc.,

hereby submb a report in accordance with H. B. Robinson Steam Electric Plant, Unit No. 2, Technical Specifications (TS) Section 3..33, P Aident Monitoring i mentn, and TS 5.4.6, Past Accddent Moitloring Instrumentation Report.

The repg O*h~k-s provided asi t ftacinetofthiete, Isbasedon theinoperability of the Wide Range Containment Pressure Tlansmitter.

The Wide Range Cont&ment Pressure Transmitter (PT)-5 will be post maintenance tested and retured to OPERABLE status prior to restart from the next refuelin outage, which is currently scheduled to begi on Septembor14, 2013, or during the first outage of sufficient duration.

If you soul have any questions concerning fts matter, please contac Ricard Hightower, Supervso - Regulatory Affalre at (843) 857-1329.

Sincerely, Sharon A. Wheeler-Peavyhouse Manager - Support Services - Nuclr Attachaent SWP/sc Mr. S. P. Ungavm, NRC rtlect Manager, NRR

'3/4, NRC ResiderKt1tnspector ~

....... 6

/4-o/

Unied Sta. Nucer Reatory CommISSon Attsachmet to Serial: RNP-RA1I3-0079 Page I of 2

. . RO1SO STEA, ELECTRIC PLANT, UNIT NO. 2 TECHNICAL SPECIFICAMIONS SECTION 6*1 POST ACCIDENT MONITORING INS UMENTATION 144DAY'

-Rm* EMR TM M, Bo M COTEM 99 MU RU MI TRAsNrIT-TE Event Description On July 17, 2013, Pressure Tranwsmtter (Pt)-968 was found out of tolerance during the performance of a Preventive Maintenance (PM) Procedure. The as found voltage reading should have been 42 VDC +/- 1 Volt and the AC Ripple Voltage should have been less than 20mVAC. During the perfrance of the PM the as found readings were 56.84 VDC and the AC Ripple Voltage was 61.18mVAC.

It was determined that PT-956 was out of tolerance due to a faulty power supply which has been replaced. However, because of the complexity of the post maintenance test to determine OPERABILITY of PT-956 it is preferred that the test be scheduled to be completed during the Refuellng Out4iiagecrrety scheduled to star on Septembe 14, 2013.

The actions for Technical Specifications (TS) Section 3.3.3, Post Accident Mnftrn (PAM)

Instrumentation, Table 3.3.3-1, Function 8, requires an Inoperable containment prosur monitoring channel to be restored to OPERABLE status within 30 days. If this indication Is not restoredwIthin 30 days, a report in accordance with TS 5.6.6 Is required within the following 14 days. TS 5.6.6 states that the report shall quftine the preplanned alternate method of mitoring, the camu of the lnoperabiltyk,and th plansand schedule for restoring the channel to operable status. The Plant Nuclear Safety Committee (PNSC) will review the Corrective Action Program investigation for this event in aocordance with the Updated Flnal Safety Analysis Repot requirements for PNSC review of reportab events.

Pleplanned Alternate Mthod of Monitorin Standing Instruction 13-012, effective 08/05/2013 for PT-956, Containment Vessel (CV) Wide Range Pressure Transmitter, outlines the alternate meh of monitoring oontainment pressure until PT-956 Is returned to service:

Hourly Monfto Capabt:

• Average Containment Pressure hourly via ERFIS Point CVP0001 Event Based Monitoring Capability

" Pressure Indicator (PQ)-957, CV Wide Range Pressure (Post Accident Monitoring Panel)

" PI-950, 951,952, 953, 954, and 955 Safeguards Containment Pressure (Reactor and Turbine Generator Board (RTGB))

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RN13-0079 Page 2 of 2 These indications are Vernded hourly or periodically on the RTGB, and as triggered by an event by the control room operators. Annunciators are also available to alert the Control Room to adverse CV pressure conditions. Should any of these indications fagl, a work order will be Initiated and worked on an emergent basis to ensure that the back-up methods for monitoring remain In place.

The TS Bases for TS 3.3.3, as it pertains to the wide range containment pressure monitoring channels, states:

"Contalnment Pressure (Wide Range) Is provided for verification of RCS and containment OPERABILITY.

Containment pressure is used to provide indication of whether the overall containment cooling function provided by containment spray and fan coolers is being achieved. Containment pressure Is also used to verify the Containment Pressure-High SI signal and the Containment Pressure-High High Spray and Steam Line Isolation Signals."

As stated in the TS Bases for TS 3.3.3, the wide range containment pressure monitoring channels provide a verification Indication. This monitoring capability does not directly Impact safety systems or the ability to mitigate the consequences of an accident.

Cause of the n r y This event has been entered into the H. 8. Robinson Steam Electric Plant, Unit No. 2, Corrective Action Program. The cause of the PT-956 inoperability was an out of tolerance power supply voltage. The power supply has been replaced, but the wide range containment pressure monitoring channel associated with this pressure transmitter cannot be confirmed OPERABLE until a Local Leak Rate Test (LLRT) can be performed.

Plan and Schedule for Reetorn the Channe The PT-956 wide range containment pressure monitoring channel cannot be calibrated without removing two (2) channels of containment pressure from service to perform the LLRT, hence, it is preferable that this calibration be done while the unit is offline for refueling. Therefore, PT-956 wide range containment pressure monitoring transmitter will be Local Leak Rate Tested and calibrated prior to restart from the next refueling outage, which is currently scheduled to begin on September 14, 2013, or during the first outage of sufficient duration.