05000315/LER-2019-002, Condition Prohibited by Technical Specification Due to an Inoperable Steam Generator Stop Valve Dump Valve

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Condition Prohibited by Technical Specification Due to an Inoperable Steam Generator Stop Valve Dump Valve
ML19333B815
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 11/26/2019
From: Lies Q
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2019-55 LER 2019-002-00
Download: ML19333B815 (7)
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LER-2019-002, Condition Prohibited by Technical Specification Due to an Inoperable Steam Generator Stop Valve Dump Valve
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(1)
3152019002R00 - NRC Website
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text

m INDIANA MICHIGAN POWEJI*

A umt of Amencan Electric Power November 26, 2019 Docket No.: 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Donald C. Cook Nuclear Plant Unit 1 LICENSEE EVENT REPORT 315/2019-002-00 lndlena Michigan Power Cook Nuclear Plant One Cook Place Bndgman, Ml 49108 lnd1anaM1ch1ganPower com AEP-NRC-2019-55 10 CFR 50.73 Condition Prohibited by Technical Specification Due to an Inoperable Steam Generator Stop Valve Dump Valve In accordance with 10 CFR 50.73, Licensee Event Report (LER) System, Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 1, is submitting as an enclosure to this letter the following report:

LER 315/2019-002-00: Condition Prohibited by Technical Specification Due to an Inoperable Steam Generator Stop Valve Dump Valve.

There are no commitments contained in this submittal.

Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Director, at (269) 466-2649.

Sincerely,

(?~A-~

a.sCues Site Vice President MPH/kmh

Enclosure:

Licensee Event Report 315/2019-002-00: Condition Prohibited by Technical Specification Due to an Inoperable Steam Generator Stop Valve Dump Valve

U. S. Nuclear Regulatory Commission Page 2 c:

R. J. Ancona - MPSC R. F. Kuntz - NRC Washington DC EGLE - RMD/RPS NRC Resident Inspector D. J. Roberts - NRC Region 111 A. J. Williamson - AEP Ft. Wayne AEP-NRC-~019-55

Enclosure to AEP-NRC-2019-55 Licensee Event Report 315/2019-002-00 Condition Prohibited by Technical Specification Due to an Inoperable Steam Generator Stop Valve Dump Valve

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)

Esbmated burden per respollMl to comply wrth !hrs mandatory collecbon request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> LICENSEE EVENT REPORT (LER)

Reported lessons learned are 11c:orporatad into the IICallnlg process and fad back to

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industry Send comments regarding burden estJmata to the lnformabon Services Branch (T-2 F43), US (See Page 2 br requred number of dlgJts/characle for each block)

Nuclear Regulatory

Coomiwon, Waohington, DC 20555-0001, or by

&-fMII to lnfocollecta Resource@TV"C gov, and to the Deok Officer, Office of lnformabon and Regulatory (See NUREG-1022, R3 for 1nstrucbon and gudance for completmg this form Affarrs, NEOB-10202, (3150--0104), Offlca of ~t and Budgst, Wa.shrngton, DC 20503 ~

a ~ns used to impose an mfonnabon collecllon does not display a currently val,d 0MB control btlo //www.rcc 92v/read109:rm/doc-coOecoons/01Jreas/staff/sr1022/r'?!/)

nurmer, the NRC may nol conduct or oponeor, and a P"ll '" not requred to re.pond to, the rnfoonatron collacbon

.PAGE Donald C. Cook Nuclear Plant Unit 1 05000315 1 OF4

4. TITLE Condition Prohibited by Technical Specification Due to an Inoperable Steam Generator Stop Valve Dump Valve
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILmES INVOLVED YEAR rEQU:4 REV FACILITY NAME bOCKET NUMBER MONTH DAY YEAR NO MONTH DAY YEAR NIA

!05000 NUMBER FACILITY NAME bOCKET NUMBER 05 29 2019 2019 002 00 11 26 2019 N/A

!05000

9. CFERAffiG MODE
11. THS REPORT IS Sll3MITTED PURSUANT TO THE REQUREMENT5 OF 10 CFR §: (Check all that app/'/)

1 D 20.2201(b)

D 202203(aX3X1)

D 50.73(a)(2)(11XA)

D 50.73(a)(2)(vm)(A)

D 20.2201(d)

D 202203(aX3)(TI) 0 50.73(a)(2)(1IXB)

D 50.73(a)(2)(v1h)(B)

D 20 2203(a)(1)

D 20.2203(aX4)

D 50 73(a)(2)(111)

D 50 73(aX2)0x)(A)

D 20.2203(a)(2)0)

D 50.36(cX1)(1)(A)

D 50 73(a)(2)(1v)(A)

D 50.73(aX2)(x)

10. POWER LEVEL D 20.2203(a)(2)(11)

D 50.36(cX1)(11)(A)

D 50 73(a)(2Xv)(A)

D 73.71(a)(4)

D 20.2203(a)(2)(111)

D 50.36(cX2)

D 50 73(a)(2Xv)(B)

D 73 71(aX5) 100 D 20.2203(a)(2)(rv)

D 50.46(a)(3XII)

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

D 73.77(aX1)

D 20 2203(a)(2)(v)

D 50.73(a)(2)(1)(A)

D 50 73(a)(2Xv)(D)

D 73.77(aX2)(1)

D 20.2203(a)(2)(vi)

[81 50.73(a)(2X1XB)

D 50.73(a)(2)(vil)

D 73 77(aX2)(11)

D 50.73(a)(2X1XC)

D Oll-iER Speafy n Abstract below or in NRC Form 366A

12. LICENSEE CONTACT FOR THIS LER

'*~*~= CONTACT rl'E NU'-'3ER (Include Araa Coda)

Michael K. Scarpello, Regulatory Affairs Director (269) 466-2649

13. COMPL.ElE ONE LINE FOR EACH COMPONENT FAIWRE DESCRlB8J IN THS REPORT

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO ICES FACTURER TO EPIX X

SB DV FISHER y

14. SUPPLEMENTAL REPORT EXPECTED
15. EXPECTED MONTH DAY YEAR 0 YES (If yes, complete 15 EXPECTED SUBMISSION DA TE)

~ NO SUBMISSION DATE MSTRACT {l..lmlt lo 1400 spBC83, 1 e., ap(YOXimately 14 smgle-spaced typewnttoo Imes)

On May 6, 2019, 1-MRV-222, Steam Generator 2 Stop Valve Train 'B' Dump Valve, was stroke timed in Mode 4, coming out of the U1 C29 refueling outage. The valve stroked in approximately 4.4 seconds with an allowable time of 2.0 seconds. A second stroke was performed and the valve appeared to stroke much faster. After the packing was wetted, the valve was then retested and passed with a stroke time of 1. 76 seconds.

On May 29, 2019, 1-MRV-222 was stroked for its quarterly test, and again failed with a stroke time of 6.84 seconds.

A Past Operability Determination Evaluation was performed and concluded that 1-MRV-222 was inoperable from May 7, 2019, when Unit 1 entered Mode 3, until it passed its surveillance after being repacked and tested on May 30, 2019.

The time period over which 1-MRV-222 was inoperable exceeded the time allowed by Technical Specification (TS) 3.7.2, SGSVs. Unit 1 also entered a Mode of applicability with 1-MRV-222 inoperable, which is prohibited without meeting LCO 3.0.4.

Therefore, this event is reportable as an Operation or Condition Prohibited by TS in accordance with 10 CFR 50. 73(a)(2)(i)(B).

NRG FORM 366 (04-2018)

EVENT DESCRIPTION

3. LER NLMBffi SEQUENTIAL NU"3ER
- 002 REV NO
- 00 On May 6, 2019, 1-MRV-222, Steam Generator 2 Stop Valve [SB][ISV] Train 'B' Dump Valve [DV], was stroke timed in Mode 4, coming out of the U1 C29 refueling outage. The valve stroked in approximately 4.4 seconds with an allowable time of 2.0 seconds. A second stroke was perfonned and the valve appeared to stroke much faster. After the packing was wetted, the valve was then retested and passed with a stroke time of 1. 76 seconds.

On May 29, 2019, 1-MRV-222 was stroked for its quarterly test, and again failed with a stroke time of 6.84 seconds.

Technical Specification (TS) Limiting Condition for Operation (LCO) 3. 7.2, requires four SGSVs and their associated actuator trains (including dump valves) to be OPERABLE, in MODE 1, and MODES 2 & 3 except when all SGSVs are closed. If one SGSV actuator train becomes INOPERABLE, the REQUIRED ACTION is to restore the actuator train to OPERABLE status within 7 days. If this 7 day COMPLETION TIME is not met, then the associated SGSV is required to be declared inoperable.

One SGSV inoperable in MODE 1, has a REQUIRED ACTION, to restore the SGSV to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. If this COMPLETION TIME is not met, then the Unit is to be placed in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Therefore, the max time allowable, from actuator train inoperability, to the time the Unit is required to be in MODE 2 is 7 days, 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.

A Past Operability Detennination Evaluation was perfonned and concluded that 1-MRV-222 was inoperable from May 7, 2019, when Unit 1 entered Mode 3, until it passed its surveillance after being repacked and tested on May 30, 2019. The time period over which 1-MRV-222 was inoperable exceeded the time allowed by TS 3.7.2, SGSVs.

Also, since LCO 3.0.4 is applicable to TS 3.7.2 for Unit 1, entry into a Mode Of Applicability for TS 3.7.2 without meeting the LCO is prohibited. Therefore, entering a Mode Of Applicability (MODES 2 & 3 except when all SGSVs are closed, and MODE 1) with 1-MRV-222 inoperable is prohibited with LCO 3.0.4 requirements not met.

Therefore, this occurrence is considered reportable as an Operation or Condition Prohibited by Technical Specification in accordance with 10 CFR 50. 73(aX2)(i)(B). Page 2 of 4 (04-2018)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 Estimated blM'dan ?61" response lo comply v.,th tln8 mandatory collection request BO hours

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LICENSEE EVENT REPORT (LER)

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CONTINUATION SHEET Regojalory Commisslorl, Wrmtmglon, DC 20555-0001, or by e-m01I to lnfocol1ects Res=ce@nrc gov, and to the Desk Officer, Office of lnlormatioo and Regulatory t------------------------t AlfaJrs, NEOB-10202, (3150-0104), Office of Mmagement and Budget, Washmgton, DC 20503 If a (See NUREG-1022, R 3 for lflStruction and guidance for completing ttus fonn ht!D:/twww.nrc oov/read1nq-rrn/doc-couections/ooroos/staff/sr1 omr3{)

1. FACIUlY NAME Donald C. Cook Nuclear Plant Unit 1 05000315 COMPONENT means used to impose an mlorma~on collection doe! not dJsplay a currendy valid 0MB corrtrol rn,nber, the N RC may not conduct or sponsor, and a person IS not reqwred lo respond to, the 1rvormallon collec!ion YEAR 2019
3. Lffi NlMBER SEQUENTIAL NUMBER
- 002 REV NO
- 00 1-MRV-222, Steam Generator 2 Stop Valve Train 'B' Dump Valve

CAUSE OF THE EVENT

During the initial failure, on May 6, 2019, an incorrect assumption was made that the packing would be wetted once steam was on the valve. Therefore. after the initial failure, the packing was wetted to simulate system operating conditions. The valve was then retested and passed with a stroke time of 1. 76 seconds.

When the quarterly stroke time surveillance was conducted on May 29, 2019, the valve did not pass.

Further investigation determined that wetting of the packing does not occur with the system in operation, with this valve, and therefore the packing had time to dry out, resulting in an increased stroke time.

ASSESSMENT OF SAFETY CONSEQUENCES

NUCLEAR SAFETY Each SGSV has a pair of dump valves that operate in complete redundancy. This means that only one of these valves needs to open for the adequate removal of steam head.

Since 1-MRV-221 (Steam Generator 2 Stop Valve Train 'A' Dump Valve) was available, limiting the impact the sole failure of 1-MRV-222 has on plant risk, there was no significant increase to the likelihood of a nuclear safety hazard resulting from the inoperable SGSV Dump Valve.

INDUSTRIAL SAFETY There was no actual or potential industrial safety hazard resulting from the inoperable SGSV Dump Valve.

RADIOLOGICAL SAFETY There was no actual or potential radiological safety hazard resulting from the SGSV Dump Valve.

PROBABILISTIC RISK ASSESSMENT Probabilistic Risk Assessment of the event determined it to have very low safety significance. Page 3 of 4

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)

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Estimated bu"dan per response to comply wrth tlus mam!atOI)' calecbon requasl 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> Repor1ed lessons leemed are 111C011)11T81ed llllo the kC8!181ng proce55 and fed back to llldustry LI C E N S E E EVE N T RE PO RT { LE R)

Send C001ITl8l1!8 regarong bu"den estunate to the Information Services Branch (T-2 F43), U S. Nuclear CONTINUATION SHEET Regi,jalo!y CommillSIO!l, Washrlgton, DC 20555-0001, or by IHllwl to lrifocollecls Resource@rl'c rp,1, and to the Desk Ofllcer, Office of lrrormellon and Reg.Jlalory 1------------------------t Affa!rs, NEOB-10202, (3150--0104), Office of MEra<Jelllanl end Budget, Washington, DC 20503 If a (See NUREG-1022, R 3 for Instruction and guidance for completJng this form htto://w'ww nrc goy/readlna-m,/doc-co!lecbons/nuregs/staff/sr1022./@

meens l.158d to llllpOS8 en mformatron collecbon does not ~splay a currently valid 0MB control number, the N RC may not conduct or sponsor, end a pooon 18 nol req.Jlred kl respond to, the l!1fonn allo n col lecboo

1. FACIUTYNAME 2 DOCKET NUMBER YEAR Donald C. Cook Nuclear Plant Unit 1 05000315 2019

CORRECTIVE ACTIONS

SEQUENTIAL NU"'3ER

- 002 REV NO
- 00 An acceptable temporary packing configuration was installed on 1-MRV-222, and the valve subsequently passed the stroke time surveillance. The permanent packing configuration will be installed during the next scheduled Unit 1 Refueling Outage in Fall of 2020 (U1C30).

PREVIOUS SIMILAR EVENTS

Licensee Event Reports for Cook Nuclear Plant Units 1 and Unit 2 were reviewed for the previous five years and found no similar events.

NRG FORM 386A (04-2018)

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