ML19095A500

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Submit Licensee Event Report Nos. LER 78-017/03L-0 Re Not Documenting Four Electric Maintenance Procedures & Two Periodic Tests, & 78-020/03L-0 Re Suspended Air Bubbles in Reservoir Fluid
ML19095A500
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/28/1978
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: O'Reilly J
NRC/RGN-II
References
Serial No. 436 LER 1978-017-03L-0, LER 1978-020-03L-0
Download: ML19095A500 (6)
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  • Mr. _James.I'. o Reilly, Director:*

Of £:I.ca of Inspection and Enforcement

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-..u. s~ *Nuclear-. Regulatory C.o.:nmie~icn ..* Docket . No.* ~tj:..;,280_* . -

  • Reg:foo: II~ Suite 818- _ *. _"-*.... * , **. License. No. - ~R.;..3*2 230 _Pea~ti.:'.ee Street~ Northwest-' .
  • Atlan*ta,_ Georgia;,'. *.30303 _- -
  • .rieai:' Mr." *o'P~illy:

. * :.Pursuant* to. Sui'ry )?ower _Station' T~chnical Spacif ica.t:tons ~ _t11e '.V'irginia Elect:rlc -

and Power**company 'hereby* submits_ t.he'.following* Licenriae. E~erit Report£ for Surr;i Uri.it

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  • . Rep9rt )10.: * . '\. *.. i~ppli~ble Teclinica~ .Specification -.
  • . LER..:78-017/031;..0.' -T~:s. 6~6~2.b.(2)

LER 78~020/03L:-P iI'~- :S# 6.?.2~_b~(2)

'fhesc repoi*ts 1{avG\ heeil ravi~rc:d: by - t~.e.. Stat ion Nuclenr Saf e,ty ~nd. Ojierating Co;n...~ttee and *will *be placed. on the a.g'enda fol:* the n.e.:Kf::. meet;f;iig of. the Syste;;i Nuclear.

I Safety and _Op~~ra.tiug Comm:ttt~a*.

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Enclosures* <<'.3, -cop~es) ... ,. .. *::.. __ . *. . .. '

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of _*.In0pectio~ and J3n.forcsncnt . , , ..' * *.

. Mi:~ Willimn G.** McD~nald, phe;~t6ri(3-~0pi~s) < ., :

..*.Of:i,:i(!(;~ .of, M!iuagGll'..1en.t:*'.1nforaac_ioh ..

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WiENSEE EVENT REPORT

  • '.' C~~TROL BLOCK: ..__~-~~-~-~ic~G) 6 (PLEASE PRINT OR TYPE ALL .UIRED INFORMATION)

~*,VI A I s Ip Is I 1 101 0 IO I - IO IO IO IO IO I- IO IO IG)!4 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 11 11 11 11 101 LICENSE TYPE 30 I 10 57 CAT *58 CON'T illTJ ~~~~~~ W©I oj s lo I oj 012 Is lo 1010 17 10 16 17 js IG)lo 17 12 17 17 I s!G) 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I On 7/6/78, during zero power physics testing, while performing PT-39A, snubber 1-RH-I~))] I HSS-10 was observed with air bubbles suspended in the reservoir fluid. A close in-

[Q]I] I vestigation r.evealed that the bubbles appeared to be coming out of the fluid line

]~IIJ I connecting the reservoir to the valve block. Since the unit was not at power, the

))))] I health and safety of the public were not affected. This is reportable in accordance I~ID !with Technical Specification 6.6.2.b.(2).

7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION t::;'\ LER/RO CVENT YEAR REPORT NO. CODE TYPE NO.

"-Y REPORT NUMBER I 71 8 J l=J I OI 2 1 .£J I/I l OI 3 I ~ l=:J ~

21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

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43 I44 1 1 2 1°I 7 1@ 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

j The air bubbles may have appeared due to the reduced pressure in containment. How-O]JJ ever, the snubber was replaced as a conservative and prudent maintenance practice.

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_J 80 FACILITY STATUS  % POWER OTHER STATUS

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\::::;J METHOD OF DISCOVERY DISCOVERY DESCRIPTION ~

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RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE @

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NUMBER .Q TYPE DESCRIPTION 39 ITEi I 0 1 °1 ~~@

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NUMBER DESCRIPTION 41 DJil I 01 7 8 9 01 01@1 11 1 N/A

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  • .77)

LIENSEE EVENT REPORT

  • CONTROL BLOCK:

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~*!VIAis IP 8 9 LICENSEE CODE 1s 11 JG)IO 10 I- lo !o lo lo lo 1-1 olo 14 15 LICENSE NUMBER 10!4 11 25 26 I 1!

LICENSE TYPE 1! 1101 30 I 10 57 CAT 58

!CON'T IE] ~~~~~~ 0 WG) 1o I s I a I oI oI 21 s Io J01 o l 6 l 3 Io I7 1s I© Io I 7 12 1s I7 1s IG) 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

jWhen presented to the Station Nuclear Safety and Operating Committee for review, pro-

~ 1cedure deviations for four electric maintenance procedures and two periodic tests did

~ 1not document Senior Operator concurrence prior to implementation. This is contrary to I III}J IT. S. 6.4.D and is reportable per T. S. 6.6.2.b.(2). Investigation indicated that SROJ

))))] 1concurrencehad been received but documentation was not completed promptly.

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7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7

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9 10 11 12 13 18 19 20 SEQUENTIAL OCCUR REN CE REPORT REVISION

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21 22 23 24 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~- ATTACHMENT NPRD-4 PRIME C.OMP .. COMPONENT*

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!Personnel conducting the procedures incorrectly assumed that. since verbal concurrence

[I]J] 1was given, that documentation could be completed coincident with completion of the pro-,

IIITI icedures. Affected personnel have been re-instructed.

CillJ L - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - , . - - - - - - - - - - J

-ITITI 7 8 9 80 FACILITY METHOD OF ~

STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION DlJ l!:....J@ I O I O 1~@1-L___N_/A_ _ -! ~Civ~l__.,-__s_t_a_t_i_o_n__c_o_m_m_i_t_t_e_e__R~e_v_i_e_w_____.

7 8 9 10 12 1'.l 44 45 46 80 ACTIVITY CONTENT ~

RELEASED OF RELEASE AMOUNT OF ACTIVITY~ LOCATION OF RELEASE @

[IE! ~ @ ~(§) 1-I*_ _ _ N_/_A_ _ _- - J N/A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES (:;;\

NUMBER r:;:;.., TYPE DESCRIPTION~

IITI j O j O IOJ0.?J~@1--_ _ _ _N/_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____,

8 9 11 12 13 80 PERSONNEL INJURIES Q NUMBER DESCRIPTION6

}li] ~0 IO 1@1....-_ _ _ _ _ ___:N/_A_ _ _ _ __;___ _ _ _ _ _ __:..__ _ _ _ ---..1 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY '43' TYPE DESCRIPTION ~

iTIJ ~@1.-L_______~__N_/A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____.

8 9 10 80 PUBLICITY f,..?-i NRC USE ONLY ISSl,.IEDQ DESCRIPTION~ "'

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8 9 10 68 69 80 ;

T. L. Baucom PHON E:--'(~8_0_4,_)_3_5_7_-_3_18_4____ 0 0.

NAME OF P R E P A R E R - - - - - - - - - - - -

  • Surry Power Station, Unit 1 Docket No. 50-280 Report No. 78-020/03L-O Event Date: 07-06-78 Replaced Snubber
1. Description of Event:

On 7/6/78, during zero power physics testing, while performing PT-39A, snubber 1-RH-HSS-10 was observed with air bubbles suspended in the reservoir fluid. A closer investigation revealed_that the bubbles appeared to be coming out of the fluid line connecting the reservoir to the valve block; This is reportable in accordance with Technical Specification 6.6.2.b.(2).

2. Probable Consequences of Event:

The problem was discovered and corrected before power escalation began.

More importantly, the snubber was still capable of performing its intended function in the 11 as-found 11 condition.' Therefore, the health and safety of the public was not affected by this occurrence.

3. Cause of Event:

The air bubbles may have appeared due to the reduced pressure in contain-ment. The unit was free of air when reinstalled after functional testing.

4. Immediate Corrective Action:

Although the snubber was considered operable, it was replaced with a shop spare as a conservative and prudent maintenance practice.

5. Scheduled Corrective Action:

. Since the snubber was replaced, no additional corrective action was neces-sary.

6. Actions Taken to Prevent Recurrence:

None.

7. Generic Implications:

This condition has not appeared in other snubbers in the system and therefore is not considered a generic problem.

Surry Power Station, Unit e, nocket No: 50-280

  • Report No: 78-017/03L-0
    • Event Date: 6-30-78 Irregularities in Use of Procedure Deviations*
1. Description of Event:

When presented to the Station Nuclear Safety and Operating Committee on 6-30-78 for review, procedure deviations for four electrical maintenance pro-cedures and two periodic test procedures displayed irregularities in handling; specifically, the deviations, while not altering the intent of the individual procedures, had not been approved in writing by a Licensed Senior Operator prior to implementation. On detailed investigation it was determined that a Licensed Senior Operator had been consulted, and had concurred in the necessity and method of deviation prior to implementation, however, these facts were not support by the written documentation. This condition is contrary to Technical Specification 6 .4 .D. and is reported in accordance with Technical Specification 6.6.2.b. (3).

The unit was in refueling shutdown.

2. Probable Consequences/Status of Redundant Systems:

The four electrical maintenance procedures covered preventive and corrective maintenance to motor operators for valves and performance of the procedures in-volved coordinating with the operations personnel. The periodic test covered surveillance requirements for elements of the fire protection system and like-wise required specific coordination with operations personnel to obtain satis-factory results. All necessary safety precautions were observed and the intent of the procedures was not altered. The health and safety of the general public were not affected.

3. Cause:

Personnel conducting the procedures incorrectly assumed that since verbal concurrence was given, the documentation of the deviation could be completed coincident with final sign-off of the respective procedures.

4. Immediate Corrective Action:

Upon review of the affected procedures, the St~tion Nuclear Safety and Operating Committee ascertained* that the matters of prior consultation with a Senior Operator had in fact been met although not substantiated by documentation ..

5. Scheduled Corrective Action:

All station maintenance personnel have been specifically re-instructed, at scheduled training sessions on the requirements to be met when procedure deviations are deemed necessary.

e Surry Power Station, Unit 1 Docket No: 50-280 Report No: 78-017/03L-O Event Date: 6-30-78 Irregularities in Use of Procedures Deviations (Cont'd:;)

6. Actions Taken to Prevent Recurrence:

The actions taken in 5. above will prevent recurrence,

7. Generic Implications:

None.

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