05000335/LER-2016-001, Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical

Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical.

ML16230A000
Person / Time
Site:	Saint Lucie
Issue date:	07/29/2016
From:	Constanzo C Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2016-152 LER 16-001-00
Download: ML16230A000 (5)

LER-2016-001, Regarding Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical.

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function
3352016001R00 - NRC Website

text

U. S'. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re:

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Reportable Event: 2016-001 Date of Event: June 2, 2016 JUL 2 9 Z016 L-2016-152 10 CFR 50.73 Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent Inoperability and Operation Prohibited by Technical Specifications The Licensee Event Report 2016-001 is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.

Respectfully, Christopher R. Constanzo.

Site Vice President St. Lucie Plant CRC/KWF*.,

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Attachment'* '/ * ** :,,. *:

Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)

.... ;..aii~-~.. Q.

Estimated burden per response to comply with this mandatory collection request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

Reported lessons learned are incorporated into the licensing process and fed back to industry.

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Send comments regarding burden estimate to the FOIA, Privacy and Information Collections

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jl'. LICENSEE EVENT REPORT (LER)

Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory (See Page 2 for required number of Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a digits/characters for each block) means used to impose an information collection does not display a currenlly vand OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

3. PAGE St. Lucie Unit 1 05000335 1 OF 4

4. TITLE Inadequate Legacy Evaluation for Containment High Range Radiation Monitor Nonconformance with Design Accuracy Requirements Resulted in Latent lnoper-ability and Operation Prohibited by Technical Specifications

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.

MONTH DAY YEAR St. Lucie Unit 2 05000389 7

FACILITY NAME DOCKET NUMBER 6

2 2016 2016 -

001

- 00 29 2016 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)

D 20.2201(b)

D 20.2203(a)(3)(i)

D 50.73(a)(2)(i)(C)

D 50.73(a)(2)(vii) 1 D 20.2201 (d)

D 202203(a}(3)(ii)

D 50.73(a)(2)(ii)(A)

D 50.73(a)(2)(viii)(A)

D 20.2203<a><1>

D 202203(a}(4)

D 50.73(a)(2)(ii)(B)

D 50.73(a)(2)(viii)(B)

D 20.2203(a)(2)(i)

D 50.36(c)(1)(i)(A)

D so.13(a)(2)(iii)

D 50.73(a)(2)(ix)(A)

10. POWER LEVEL D 20.2203(a)(2)(ii)

D 50.36(c)(1}(ii)(A)

D 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x)

D 20.2203(a)(2)(iii)

D so.36<c><2>

D 50.73(a)(2)(v)(A)

D 13.11(a)(4) 100 D 20.2203(a)(2)(iv)

D so.46(a)(3}(ii)

D 50.73(a)(2)(v)(B)

D 13.11<a><sl D 20.2Z03(a)(2)(v)

D 50.73(a)(2}(i)(A)

D 50. 73(a)(2)(v)(C)

D OTHER D 20.2203(a)(2)(vi)

~ 50.73(a)(2}(i)(B)

D 50.73(a)(2)(v)(D)

Specify in Abstract below or in LICENSEE EVENT REPORT (LER}

CONTINUATION SHEET

1. FACILITY NAME

2. DOCKET St. Lucie Unit 1 05000335

• Description of the Event Estimated burden per response to comply with this mandatory collection request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

Reported lessons learned are incorporated into the licensing process and fed back to industry.

Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budge~

Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB conbol number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

YEAR 2016

6. LER NUMBER I

SEQUENTIAL I NUMBER 001 REV NO.

0 2

3. PAGE OF 4

On June 2, 2016, St. Lucie Units 1 and 2 were in Mode 1 at 100% power. As discussed in the NRG design basis inspection report 05000335/2016010 and 05000389/2016010, FPL's 1997 evaluation of previous containment high range radiation monitor (CHRRM) [EllS:IL:RM] industry Operating Experience (OE) had incorrectly evaluated the impact of thermally induced currents (TIC) and moisture intrusion/cabl.e blistering on Rockbe~tos/Raychem coaxial cable [EllS:IL:CBL 1] and their effect on CHRRMs operability. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, FPL declared the CHRRMs inoperable and entered the appropriate action statements for each Unit. The limiting condition for operation (LCO) for Technical Specification (TS) 3.3.3.1, Action b, Table 3.3-6, Action 15 (Unit 1) and Action 27 (Unit 2), are essentially the same and state that:

"With the number of channels OPERABLE [OPERABLE Channels - Unit 2] less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:

1) Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and

2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status."

On June 4, 2016 the preplanned alternate methods for monitoring containment radiation levels were implemented in accordance with operator night orders and enhancements made to plant procedure EPG-08, "Monitoring Plant Equipment Important to the Radiological Emergency Plan," Attachment 2, "Alternate Monitoring Method with the CHRRM Channels Inoperable."

The CHRRMs are used as one of several diverse methods for evaluating emergency action levels (EALs) for the Loss of Fuel Clad Barrier and for the Potential Loss of Primary Containment Barrier in the St. Lucie Emergency Plan (EPlan). Unit differences necessitate different strategies for the Loss of Fuel Clad Barrier EAL determined by CHRRMs indication. These preplanned alternate methods use:

the containment isolation radiation monitors (Unit 1), or the diverse indications as defined in the EAL table to evaluate the loss of the fu13l clad barrier (Unit 2) (e.g.

core exit thermocouples, Dose Equivalent 1-131, loss of the core heat removal safety function and entry into emergency operating procedure EOP-15)

The Potential Loss of Primary Containment Barrier EAL determined by CHRRMs indication will be provided in part by the use of the post-LOCA radiation monitors with outside containment radiation levels that correlate to the radiation levels inside containment.

Two inoperable CHRRMs require that the NRG be notified of this condition in accordance with TS 6.9.2. FPL submitted the special report on July 16, 2016, in FPL letter L-2016-127.

Cause of the Event

In 1997 and 1998, NRG Information Notice (IN) 97-45 and its !)upplement 1 notified the industry that the CHRRMs were subject to erratic behavior and possible failure because the expected post-accident environmental conditions within containment could adversely affect the cabling system. FPL's initial disposition of the issue considered the CHRRMs operable due to the short time period the effects lasted, the bounded containment LOCA temperature profiles, and the consideration of the diverse means available for accomplishing post-accident dose assessment, core damage assessment, and emergency plan (EPlan) actions. FPL intended

1. FACILITY NAME St. Lucie Unit 1 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT {LER)

CONTINUATION SHEET

2. DOCKET YEAR 05000335 2016

6. LER NUMBER I

SEQUENTIAL I NUMBER 001 REV NO.

0 3

3. PAGE OF 4

to close out the potential cabling noncompliance issue as recommended by the Nuclear Utility Group on Equipment Qualification (NUGEQ). However, this intent was not effectively followed through by FPL and the associated tracking action was inappropriately closed by utility personnel. Failure to appropriately track actions to restore compliance is considered a 1997 legacy issue; the corrective action program (CAP) requirements for operability/functionality have been significantly enhanced in the intervening years. FPL plans to replace the subject cabling with alternates resistant to the effects noted in the IN.

Analysis of the Event

This event is reportable under 10 CFR 50. 73(a)(2)(i)(B) as "Any operation or condition which was prohibited by the plant's Technical Specifications... " The CHRRMs are designed for accuracy within a factor of 2 over the entire range for post-accident monitoring. However, this design requirement would not have been met during postulated design basis accidents (DBAs). From 1997 until June *2016, this noncompliance resulted in inoperable CHRRMs without the implementation of the required TS pre-planned alternate containment radiation monitoring methods.

The Rockbestos/Raychem coaxial cabling us.ed with the CHHRM detectors in containment is susceptible to the TIC phenomenon that can introduce transient signal errors in excess of the system's design factor of 2 accuracy requirement during short duration large temperature transients, such as those anticipated following a design basis main steam line break (MSLB) inside containment or loss of coolant accident (LOCA). These transient signal errors are directly proportional to the rate of temperature change (positive and negative) and are only functionally significant in the initial seconds to minutes of a OBA.. The TIC error induced during the initial temperature ramp of some DBAs was calculated to be in excess of 6000 Rem/hr, and quickly decayed to near zero within the first 100 seconds. As the containment cools down post-OBA, the error response will transition to a negative bias. For St. Lucie, the negative bias is expected to be less than -60 Rem/hr at 500 seconds to -8.5 Rem/hr at 3500 seconds.

Cable moisture intn5sion/blistering and other phenomenon described in IN 97-45 are driven in part from the temperature peak inside containment, and could lead to a permanent signal bias or cable failure.

FPL performed an extent of condition by reviewing the other radiation monitors at St. Lucie for susceptibility to the effects noted in the IN, and no other components relied for long-term post-accident monitoring, were identified.

Safety Significance

There are no automatic functions provided by CHRRMs on either Unit other than annunciation. The CHRRMs

• are one of the methods *utilized in the St. Lucie Emergency Plan to determine EAL entry conditions, dose assessment, and core damage assessment.

Although the postulated TIC signal error in the first 100 seconds post-OBA results in indicated radiation levels inside containment meeting* the EPlan EALs for both the Loss of Fuel Clad and the Potential Loss of Containment, that early in the event there would be no confirmatory evidence to support escalation of the emergency classification beyond the Alert Level. Based on emergency procedure sequence and licensed Operator training for event diagnosis and response, it is considered highly improbable that Operations would declare a Site Area Emergency based solely on the application of the initial containment radiation spike within the Fission Product Barrier EALs.

During the postulated post-OBA containment cooldown, the magnitude of the negative bias introduced by the TIC would be overcome by the actual radiation levels in containment, should fuel damage occur. After approximately one hour, the magnitude of the negative bias is insignificant as compared with any substantive accident dose. In addition, during a OBA with fuel damage, diverse indication for entry into higher EALs which are proceduralized and trained upon would result in licensed operators and members of the Emergency Response Organization to make the correct emergency declaration.

Moisture instrusion/cable blistering is a concern during the higher peak temperatures inside containment associated with DBAs. FPL originally concluded that this was not a concern because of the assumption that the phenomon would only occur at the higher temperatures associated with MSLB. However, the lower temperatures associated with LOCAs do not preclude this degradation mechanism and could result in a long-term erroneous signal bias.

Regardless, the diverse indications as defined in the EAL tables to evaluate the loss of the fuel clad barrier are also available and provide information on the health of the fuel clad barrier. These pre-existing diverse indication independent from CHRRMs include the core exit thermocouples, dose equivalent 1-131, loss of the core heat removal safety function, and entry into the emergency operating prqcedure Safety Function Staus Checks.

In addition to directing EPlan EAL entry conditions as described above, the CHRRMs also support Emergency Preparedness dose and core damage assessment capabilities. However, dose c:md core damage assessment continue to.be functional without reliance on CHRRMs as the pre-existing procedures and training for members of the Emergency Response Organization and Operations provide diverse means (i.e., core exit thermocouplP-s, reactor vessel water level monitoring system, reactor coolant system activity, and safety function status checks) for obtaining the required information.

Even though the CHRRMs were inoperable during of the time period of concern, diverse indication provides similar information. Therefore this event had no significant impact on the health and safety of the public.

Corrective Actions

1. Alternate pre-planned means for monitoring containment radiation levels were implemented on June 4, 2016.

2.

The 14-day TS Special Report for two inoperable CHRRMs channels was submitted on June 16, 2016.

The licensee planned actions listed below have been entered into the site corrective action program. Any changes to the actions will be managed under the corrective action program:

3.

FPL is conducting constructability reviews inside containment for cable replacement during the next refueling outages.

4.

Based on the constructability reviews and material availability, an implementation schedule will be developed and the more robust coaxial cable design will be installed within the next two refueling outages for each unit.

Failed Component(s)

Unit 1: Cable; Manufacturer: Rockestos; Model: RSS-6-104/LD Unit 2: Cable; Manufacturer: Raychem; Model: Flamtrol (XLPE)

Similar Events

None.