05000366/LER-1979-106-03, /03L-0:on 790919,several Operational Cycle & Other Surveillances Were Overdue.Caused by Misinterpretation of Tech Specs Re Starting Time for Surveillances.Exemption Requested & Granted

/03L-0:on 790919,several Operational Cycle & Other Surveillances Were Overdue.Caused by Misinterpretation of Tech Specs Re Starting Time for Surveillances.Exemption Requested & Granted

ML20136C789
Person / Time
Site:	Hatch
Issue date:	10/12/1979
From:	Coggin C GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20136C785	List: 05000366/LER-1979-106, Forwards LER 79-106/03L-0 05000366/LER-1979-106-03, /03L-0:on 790919,several Operational Cycle & Other Surveillances Were Overdue.Caused by Misinterpretation of Tech Specs Re Starting Time for Surveillances.Exemption Requested & Granted
References
LER-79-106-03L, LER-79-106-3L, NUDOCS 7910170262
Download: ML20136C789 (4)

LER-1979-106, /03L-0:on 790919,several Operational Cycle & Other Surveillances Were Overdue.Caused by Misinterpretation of Tech Specs Re Starting Time for Surveillances.Exemption Requested & Granted

Event date:
Report date:
3661979106R03 - NRC Website

text

U. S. NUCLE AH HEGUL ATONY COMMISSION

NHC F ORM 366

'D 71)

LICENSEE EVENT REPORT coNTngloco

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(PLE Asr PRINT OR TYPE ALL HEOUlHED INFOnMATION) l0 l'l LoJ/t lIJ_1J.1!J__2JOI o I o i o I o l o I o I o 1 o I oJ_of a t@!411 Il 11 11 i

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EVENT DESCRIPTION AND PROBACLE CC'dEff)ENCES h with the reactor in steady state power operation, a review of l

lfo_UU { On September 19, 1979, [o L.O burveillances required by the Technical Specifications showed that a number of opera i

d to be_ done on an interval of at least once 1

I o 141 Lionc.t1_.c.yc1c_surveiUanc.nj.tttoce_ te!LLL rA d other surveHlances.1 required to be done on an interval of at leastj 8 L pe t_18 rf m Lb al_.M t LEji] Lance _per_.l.,ycarsl_werEnv.erdum._iA_they 3iere not performed within the allottedJ l ' 1 LJ.ica_ir<terv1Lalus_tbe_ ass.orjAteLatacemdasiJ257, of the surveillance intervall J

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[ Attached is a listing of all such surveillances showing due dates.

C O*.W VALVE SYS f E M

CAUSE

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31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECDVE ACTIONS h cause__of the event was a mis-interpretation of the Technical Specification in

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1__i 101 LItc The licensee bel-l LLLL.J [ reqanLip the startinq time for the aforetrentioned surveillances.

[TT 1 L ieved that the time startina point was,the date of the receipt of the operatinq lic-I furthnrmore, the licensee believed that this interpretation had l

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[J_Jd.J 1 the concurcq11cp of the NRC.

However, a cnnversatine, with thn Npr nn con tinuedh 83 7

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Event Description and Probable Consequences a result of this event; there is no There are no probable consequences asThis is a non-repetitive event.

ef fect on public health or safety.

Cause Description and Corrective /,ctionsshowed that the NRC's current interpretation fixes the start-17, 1979, time at either the first time the procedure was performed or the twe September at which another test was perforuied to prove system operability prior to the ing system being placed in service (if the surveillance was never performed).

Corrective action for all of the surveillances except HilP-2-3359 was to request Technical Specification exemption for the surveillance to allow the licensee to wait until the scheduled outage of March 1979, to perform the surveillances; the exemption was granted in Technical Specification Amendment Number 12 on September 21, 1979.

Performance of HNP-2-3359 was begun on October 10, 1979.

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Description

Tech Spec.

I n i t t. a 1 Due 1.atest Possible

.Wer Reference Performance Data Dste Data II'!i! C 5i'IT~~~~

APRM Tir.e Resoonse Table 1.3.1-2a, b ------

Overdue 2

Test HNi-->'

'q Coca Spray Auto 4.5.1.1.d 10-1-77 4-1 74 5-15 74 A.,

Actuntion

""pAF-'

Safetv Pelief' C5. 6 5-11 77 2-11-79 CC79 Valve Operability H"P

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2'o' dPCI 'J a l v e Operab- ~C69 E-17 77 P-17-74 7-1-70

)

111tv (Stem Move-ment Verification 1

k-g u ; S i' i Fire Hose Overdue q

Station Insoection f

o t P- ?

o RCIC Valve Operab-CO. 5

!I-1-77 2 T74 ti-15-79 111tv ('1 tem Move-nant Varification Rectreulation Sys-CO. 5 10-25 77 C?T79 0 E-70

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tem Valve Operat-111ty (Stem Move-ment Verification m?b4 Seactor Recire Dmo C6. 2. 6.1. a.1. ( b )

9-12-77 b1?-70 7-P C7Q Motor Protection Sys tm Integrated L.

Functinnal Taat

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2 SLC Tast Actuation 4.0.5, 4.1.5.c 11-2-77 6-2-70 0-1K-79 Frns Control Room 3.1.?-1(3d)

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bydradiic S ma b b e r 4.7.h.4 Overkue F u n c t i ce, a 1 Test h

h.,.6.1.1.b,d 11-2-77 5-2-70 9 - 1 r, 7 6

,t-

--' 4 '

Testing of S D:1T s

4 Filtar Trains

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9 Reactor Rectre.

C C 3.1.a.1.(a) T26~77

~10-?0-78 3-6 To I

Tunn Motor Prot-s.

action System Rel-av Calibration 2 5 #l

Triaxial Peak Rec-k.T~5.2-1(2a-2f)

Overdue 4

ordir.a Accelecom-etors Calibration Fira Protection T.7.6.1.d 0 I5-77 b 1 C7a C30 70

~

v SVSteM SV s t e f'l Flu,5 Fire Pratention 4.7 5.1.g 5-?L-7I~~

5-24

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?-? 4 7 5

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v Systan System (1-yean)

Ficu Test Diewt Fire Puma C C CT~2.c 5-2EIM 11!? C7'-

C+!76 4

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Insnantion, Start and *-ir Fir-Pm e Diesel 4.7. C C3.c Overdoa 4

ta t t oav Irsractinn 5

P00R ORINAL

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b Sprinkler Hand Air 4.7. C2.c Oveadue Flow Tast (1 year)

CO2 System Valves 4.7.6.3.5 6 ?7-74 12-?7 75 5-11 76

,L and Ds aip e r s Actust-ton a9d Flow Hosa S Gtion Valve CE63. c Overdue b

Operability and (1 year)

Hose Hydro Test Diesel Generator 4.8.1.1.2.c.4 10-25-77 4-25-79 4 T 74 b

Load Peject Capthi1ity Diesel Generator 4.6.1.1.2.c.7 10-25 77 4-25-79 Q-5-74 b

S h e d d i n a; and Sub-sequan* Loadine Diasel Generator 4.8.1.1.2.c.9 10-25-77 4-25-79 4 C7 4 b

24-houa Loaded Run Test Safety injection

4. [1.1.2.c.12 10-25-77 4-25-74 4 E-79 L

Override of Diesel Geneaatoa Tast Mode D' i e s e l Generator 4.8.1.1.2.c.11 6-16-77 12-16-78 4-30-79

'L Fuel Transfer Capsbility Molded Case Cir-4.8.2.6.1.a.2 Overdue b

cuit Breaker Func-tinnal Test a

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