ML19095A588: Difference between revisions

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Vice President-Power Supply and Production Operations Enclosure cc:  Mr. Robert.W. Reid, Chief Operating Reactors Branch 4 (40 copies AO~Sl-76-07)
Vice President-Power Supply and Production Operations Enclosure cc:  Mr. Robert.W. Reid, Chief Operating Reactors Branch 4 (40 copies AO~Sl-76-07)
* LICENSEE EVENT REPOI                                              AO-Sl-76-07                                  ~
* LICENSEE EVENT REPOI                                              AO-Sl-76-07                                  ~
                                                                                                                                                                                  .. *
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     . EVENT DESCRIPTION (can't) e cent greater than that specified. The ?me was notified S~ptember 13, 1976 of the possible violation while calculations were.being verified. At 1930 hours on September 13, 1976 a change to Section 3.11.B of the Surry Technical Speci-fications, which was submitted in August, was approved and received. The actual percent of the new technical specification limit was .3 percent. The actual verification of the violation of Section 3.11.B was complete at approximately 2200 hours, thereby documenting a violation had occurred over the last 12 months.
     . EVENT DESCRIPTION (can't) e cent greater than that specified. The ?me was notified S~ptember 13, 1976 of the possible violation while calculations were.being verified. At 1930 hours on September 13, 1976 a change to Section 3.11.B of the Surry Technical Speci-fications, which was submitted in August, was approved and received. The actual percent of the new technical specification limit was .3 percent. The actual verification of the violation of Section 3.11.B was complete at approximately 2200 hours, thereby documenting a violation had occurred over the last 12 months.
(AO-Sl-76-07)
(AO-Sl-76-07)
CAUSE DESCRIPTION  (can't) terpretation of what should be included in releases was changed on September 10, 1976. In an attempt to more accurately include certain noble gases, the annual limit was exceeded by less than .188 percent/month.
CAUSE DESCRIPTION  (can't) terpretation of what should be included in releases was changed on September 10, 1976. In an attempt to more accurately include certain noble gases, the annual limit was exceeded by less than .188 percent/month.
ADDITIONAL FACTORS (con't) olation; therefore, the health and safety of the general public was not affected.
ADDITIONAL FACTORS (con't) olation; therefore, the health and safety of the general public was not affected.
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Latest revision as of 09:45, 2 February 2020

Submit Reportable Occurrence No. AO-S1-76-07 Re Recalculation of Gaseous & Airborne Particulate Wastes Originating from Station Operation for Previous 12 Months
ML19095A588
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/24/1976
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: Moseley N
NRC/RGN-II
References
Serial No. 258 LER 1976-007-00
Download: ML19095A588 (4)


Text

VIRGINIA ELECTRIC AND POWER COMPANY RIOHMOND,VIRGINIA 23261 September 24,. 1976 Mr. Norman C. Moseley, Director Serial No. 258 Office of Inspection and Enforcement PO~/ALH:clw U.S. Nuclear Regulatory Commission Region II - Suite 818 Docket No. 50-280 230 Peachtree Street, Northwest License No. DPR-32 Atlanta, Geo.rgia 30303

Dear Mr. Moseley:

Pursuant to Surry Power Station Technical Specification 6.6.2, the Virginia Electric and Power Company hereby submits a copy of Reportable Occurrence ijo, AO~Sl-76-07.

  • The substance of this report has been reviewed by the Station Nuclear Safety and Operating Committee and will be placed on the agenda for the next meeting of the System Nuclear Safety and Operating Committee.

Very truly yours,

!ff&gf/

Vice President-Power Supply and Production Operations Enclosure cc: Mr. Robert.W. Reid, Chief Operating Reactors Branch 4 (40 copies AO~Sl-76-07)

  • LICENSEE EVENT REPOI AO-Sl-76-07 ~
  • CONTROL BLOCK: I I

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_L__J__,__---'----'

6 (PL:2.:\S!:: iPFJl:\l, AU. !;;!EQUlJ::iED ll'.!F(l!:li'iJATlON) .I LICENSEE LICENSE EVENT

'NAME LICENSE NUMBER TYPE TYPE

@El 7 8 9 l v I A I s I P! sl 1*14I I15o I o 1-1 oI oI ol o I o 1-1 oI o25I 26 1J1l1!0!

30 Io 14 I 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE 7

@E]coi'n 8

IP I 58I l!J 57 O

59

~

60 1°1 61 5

101-1 OJ 21 SI 01 loi9lll3l7J6I 1019121217l6J 68 69 74 75 BO EVENT DESCRIPTION

@12] J Due to recent interpretational changes in the intent of Section 3 . 11 . B of the Surry'  !

7 8 9 80

@El I Technical Specifications, the gaseous and airborne particulate wastes originating j 7 8 9 . 80

!oj4J I from station operation for the previous 12 months were recalculated. The results of I 7 8 9 80 rn 7 8 9 I the recalculations indicated a violation of Technical Specification 3.11.B.2 in that j 7

lliIID8 9I the monthly average for the previous 12 months was 10.188 percent or .188 per- (can't~!

PRIME 80 SYSTEM CAUSE COMPONENT . COMPONENT CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION 7

@0 8 9

!MI 10 Bj L~J 11 I x I x I xj x I x ! x j 12 17

~

43 lz I 919 19 I 44 47 w48 CAUSE DESCRIPTION

@Jfil I The level of gaseous and airborne particulate wastes were primarily related to steam 7 8 9 80

~ j generator primary to secondary tube leakages. Some procedural errors were also found I 7 89~"------~---=--------=-------=------.:_-----------.------~ , 80 IT@! I in the release calculations but the actual violation resulted because the in- (can't) j 7 8 9 80 FACILITY METHOD OF STATUS  % PO'NER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EE]

7 8 w

9 I1 Io l 0 10 12 13 N/A 44

~

45 46 N/A 80 FORM OF ACTIVITY CONTENT rn.

OF RELEASE. LOCATION OF RELEASE RELEASED LgJ jM I IN/A AMOUNT OF ACTIVITY I Vent to Atmosphere I

.7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTIDN

!Iell 0 1°1°111 ~12 N/A 1'::::3-------------------------------------8-10 7 8 9 PERS'ONNEL INJURIES NUMBER

  • DESCRIPTION 7

EB8 9lo Io I o11I N/A 1'=2-------------------------------'---------B_iD OFFSITE CONSEQUENCES

-~ N/A 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCAJPTION 7

~8 9~ N/A 10;:;---------------------------,------------------_:_-B_fD PUBLICITY

@fl8 7

~-N....:../_A-:------------..,--------------------:1 9 80 ADDITIONAL FACTORS

[1 [aj I The release described herein was well below the limits established by 10 CFR 20 and 7 8 9 80 IT@ I only . 3 percent of the Technical Specification in effect at the time of the vi- (con't)j 7 8 9 80 Tyndall L. Baucom N A M E : - - - - - - - - - - - - - - - - - ' - - - - - - - - PHONE:

(804) 357-3184 GPO 8BJ

  • 667

. EVENT DESCRIPTION (can't) e cent greater than that specified. The ?me was notified S~ptember 13, 1976 of the possible violation while calculations were.being verified. At 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> on September 13, 1976 a change to Section 3.11.B of the Surry Technical Speci-fications, which was submitted in August, was approved and received. The actual percent of the new technical specification limit was .3 percent. The actual verification of the violation of Section 3.11.B was complete at approximately 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, thereby documenting a violation had occurred over the last 12 months.

(AO-Sl-76-07)

CAUSE DESCRIPTION (can't) terpretation of what should be included in releases was changed on September 10, 1976. In an attempt to more accurately include certain noble gases, the annual limit was exceeded by less than .188 percent/month.

ADDITIONAL FACTORS (con't) olation; therefore, the health and safety of the general public was not affected.

  • 7 '