ML18152B726

LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable

ML18152B726
Person / Time
Site:	Surry
Issue date:	01/21/1999
From:	Grecheck E VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18152B725	List: ML18152B724 ML18152B726
References
LER-99-001, LER-99-1, NUDOCS 9901270157
Download: ML18152B726 (3)

Text

e NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB NO. 3150-0104 (6-1998) EXPIRES 06/30/2001

. Estimated burden par response to comply wilh this mandatory information collection request: 50 hrs. Reported lessons learned are incorporated into lhe licensing process and led back to industry.

Forward comments regarding burden estimate to the Records LICENSEE EVENT REPORT (LER) Management Branch (T-6 F33), U.S. Nuclear Regulalory Commission, Washington, DC 20555-0001, and ta the Pap8fWOfk Reduction Project (3150-0104), Office of Management and Budget, Washington, DC 20503. If an informalion collection does not display a currently valid (See reverse for required number of digits/characters for each block) 0MB control number, !he NRG may no! conduct or sponsor. and a person is not required lo respond lo, the information collection.

FACILITY NAME (1) ) PAGE (3)

SURRY POWER STATION, Unit 1 05000 - 280 1 OF3 TITLE (4)

Auxiliary Feedwater Pipe Support Missed Surveillance Due to Personnel Error EVENT DATE (5) I LER NUMBER (6) I REPORT DATE (7) I OTHER FACILITIES INVOLVED (8)

SEQUENTIAL REVISION FACILITY NAME DOCUMENT NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NUMBER 05000-FACILITY NAME DOCUMENT NUMBER 12 22 98 1999 -- 001 -- 00 01 21 99 05000-l~RATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)

DE (9) N 20.2201(b) 20.2203(a)(2)(v) X 50.73(a)(2)(i) 50. 73(a)(2)(viii)

, - .. ER 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50.73(a)(2)(x)

) 100 <<< 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50.73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50. 73(a)(2)(v) Specify in Abslract below 20 .2203( a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii) or in NRG Form 366A LICENSEE CONTACT FOR THIS LER (12)

NAME E. S. Grecheck, Site Vice President I ( ; ; ; ; N ; ; ; : ; ~ ~ l ; e Nea Code)

COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX TOEPIX SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR I (IfYESyes, complete EXPECTED SUBMISSION DATE).

IX I NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

On December 22, 1998, it was determined that two pipe supports on the cross-connect line of the auxiliary feedwater pumps had not been inspected during the second lnservice Inspection (ISi) interval in accordance with Technical Specification (TS} 4.0.5. The TS requires inspection and testing of ASME Class 1, 2, and 3 components. The supports in question were not shown on the current station drawings and as a result were omitted from the ISi Program. This event is reportable pursuant to 10CFR50.73(a)(2)(i)(B) for a condition prohibited by Technical Specifications. The two supports received Code inspection and were found fully acceptable.

Therefore, no conditions adverse to safety resulted from this event.

9901270157 990121 PDR ADOCK 05000280 s PDR I II NRG FORM 366 (6-1998)

e e NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (6-1998)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET LEA NUMBER (6) PAGE (3)

SURRY POWER STATION, UNIT 1 YEAR l SEQUENTIAL NUMBER l REVISION NUMBER 05000 - 280 1999 -- 001 -- 00 2 OF 3 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

1.0 DESCRIPTION

OF THE EVENT On December 22, 1998, with Unit 1 at 100% reactor power, a review of lnservice Inspection (ISi) isometric drawings indicated that a segment of piping, including two identified supports, was omitted from the appropriate drawings used in the Surry ASME Section XI examination program. The above review was conducted because of an industry operating experience. Techn_ical Specification 4.0.5 requires inservice inspection and testing of ASME Code Class 1, 2, 9-nd 3 components. Inspection requirements are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR 50~55a and as modified by NRG approved relief requests.

Subsection IWF of Section XI requires component supports to be examined over a ten-year interval using a sampling program. The ISi program component inspections, which satisfy the TS 4.0.5 surveillance requirement, were based on the ISi isometric drawings.

As a result, there was a missed surveillance of the supports during the second interval of the ISi inspection. This event is reportable pursuant to 10CFR50.73(a)(2)(i)(B) for a condition prohibited by Technical Specifications.

2.0 SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS Examinations of the two Class 3 supports were found to be acceptable. The supports_

would have met their design function and did not pose an operability concern. As such, there were no significant safety consequences or implications. Therefore, the health and safety of the public were not affected by this event.

3.0 CAUSE On December 22, 1998, during an Engineering assessment of drawings on the Surry Auxiliary Feedwater lines, it was identified that two supports were inadvertently omitted from the drawings used for ISi inspections. Since the supports were omitted from the drawings, the supports were not included in the examination database used to schedule inspections. As a result, the examinations were not performed in the second inspection interval (12/22/82 - 10/14/93) nor scheduled for the current third interval. The second interval, which required inspection of 100% of the supports within scope, has expired; therefore, the surveillance was not met within the required timeframe.

NRC FORM 366A(6-1998)

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" NRC FORM 366A (6-1998)

U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET LER NUMBER (6) PAGE (3)

SURRY POWER STATION, UNIT 1 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 05000 - 280 1999 -- 001 -- 00 3 OF 3 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) 3.0 CAUSE (continued)

Upon investigation, it was determined that in September 1988, three ISi isometric drawings were merged into two drawings and a segment of piping was inadvertently left out. This drawing error omitted the two identified supports from the appropriate drawings used in the Surry ASME Section XI examination program. The cause of the omission of the components from the station drawings was due to personnel error during the revision of three drawings.

4.0 IMMEDIATE CORRECTIVE ACTION(S)

A station deviation report was submitted. The two supports in question received the required Code inspection and were found to be acceptable.

5.0 ADDITIONAL CORRECTIVE ACTIONS A drawing change request was submitted to revise the drawings to include the two supports. Appropriate ISi database corrections were made.

6.0 ACTIONS TO PREVENT RECURRENCE The current process for revising ISi isometric drawings and maintaining the ISi database ensures necessary ISi inspections are conducted. Engineering will assess a sampling of drawings used for ISi examinations to determine if further corrective actions are necessary.

7.0 SIMILAR EVENTS None.

8.0 MANUFACTURER/MODEL NUMBER None.

9.0 ADDITIONAL INFORMATION Unit 2 was operating at 100% at the time of this event.

NRC FORM 366A (6*1998)