05000423/LER-1997-026, :on 970325,missed Performances of SWS Support Exams Required by ASME Section Xi.Caused by Inappropriate Decision Re Classification of These Component Supports. ISI Program Documents Will Be Revised by 970630

:on 970325,missed Performances of SWS Support Exams Required by ASME Section Xi.Caused by Inappropriate Decision Re Classification of These Component Supports. ISI Program Documents Will Be Revised by 970630

ML20138J473
Person / Time
Site:	Millstone
Issue date:	04/24/1997
From:	Peschel J NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20138J455	List: 05000423/LER-1997-026, :on 970325,missed Performances of SWS Support Exams Required by ASME Section Xi.Caused by Inappropriate Decision Re Classification of These Component Supports. ISI Program Documents Will Be Revised by 970630
References
LER-97-026, LER-97-26, NUDOCS 9705080228
Download: ML20138J473 (3)

LER-1997-026, on 970325,missed Performances of SWS Support Exams Required by ASME Section Xi.Caused by Inappropriate Decision Re Classification of These Component Supports. ISI Program Documents Will Be Revised by 970630

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
4231997026R00 - NRC Website

text

_ _ _ _ - _ _ _ - _ - _ _ - _

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OM8 NO. 3160-0104 NRC FORM 366 (4 95)

EXPIRES 04/30/98

!'70'0!& JN!"#fio"J'e~u'!s? ff"%s*"M"A"ti?N80 pa*'?o'LMP."; "';!%3,Po '"!Mla" Jc" fat'3 ^3=

LICENSEE EVENT REPORT (LER)

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(See reverse for required number of digits /CharaCtersfor eaCh block) fJ.CluTY NAME (1)

DOCKET NUMBER (2)

PAGE(3)

Millstone Nuclear Power Station Unit 3 05000423 1 of 3 TITLE let Missed Performances of Service Water System Support Examinations Required by ASME Section XI EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACILITY NAME DOCKET NUMBER

)

NUMBER j

03 25 97 97 026 00 04 24 97 OPERATINO 5

THIS REPORTIS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check one or more) (11)

MODE (9) 20.2201(b) 20.2203(a)(2)(v)

)( 50.73(a)(2)(i) 50.73(a)(2)(viii)

POWER 000 20.2203(a)(1) 20.2203(a)(3)(i) 50.73(a)(2)0i) 50.73(a)(2)(x)

LEVEL (10) 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(aH2)(iii) 50.36(c)(1) 50.73(a)(2)(v) specifY in Abstract below 20.2203(a)(2)0v) 50.36(c)(2) 50.73(a)(2)(vii)

LICENSEE CONTACT FOR THIS LER (12) j NAME TELEPHONE NUMftER l include Area Codel J.M, Peschel, MP3 Nuclear Licensirsg Manager (860)437-5840 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE

SYSTEM COMPONENT M ANUF ACTURER REPORTABLE

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE I

To NPRDs TO NPRDs l

l S UPPLEMENTAL REPORT EXPECTED (14)

EXPECTED MONTH DAY YEAR YES X NO SUBMISSION (if yes, complete EXPECTED SUBMISSION DATE).

ABSTRACT (Limit 101400 spaces,i.e., approomatelv 1 E Hngle-spacedtypewritten knes) (16)

On March 25,1997, with the unit in Mode o, a review of past inservice inspection (ISI) results concluded that the American Society of Mechanical Engineers (ASME)Section XI examinations had not been performed on some Service Water System j

(SWS) supports during the 1989 refueling outage. Additionally, one component support had not received a successive cxamination as required by Section XI, Article IWF-2420 during the second period of the inspection interval. Examination of cdditional component supports resulted in the total population of SWS component supports being required to be examined in Eccordance with Section XI, Article IWF-2430. Twenty-five component supports located in inaccessible areas were not examined.

R; lief was not requested to exclude inspecting these component supports. Failure to perform these examinations, as required by Ttchnical Specification (TS) Surveillance Requirement 4.0.5, is reportable pursuant to 10CFR50.73(a)(2)(i)(B), as a condition prohibited by the TS.

]

The apparent cause of this event was an inappropriate decision regarding the classification of these component supports as inIccessible and subsequent failure to apply for relief from these inspections.

The condition is significant because of the resultant operation in a condition prohibited by the Technical Specifications.

However, there were no safety consequences due to the event, in that, the twenty-five Service Water System component supports which were considered inaccessible in 1989, when subsequently inspected, were determined to be acceptable.

Guidance will be added to the ISI program for the ASME Section XI requirements for performing additional and successive cxams and requesting relief from code requirements.

9705000228 970424 PDR ADOCK 05000423 S

PDR

.U.S. NUCLEAR RE2ULAToRY CoMMisslON LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILirY NAME (1)

DOCKET NUMBER (2)

LER NUMBER (6)

PAGE (3)

YEAR SEQUENTIAL REVISloN Millstone Nuclear Power Station Unit 3 05000423 NUMBER NUMBER 2 of 3 97 026 00 TEKT (If more space is required, use additionalcopies of NRC Form 366A) (17) 1.

Description of Event

On March 25,1997, with the unit in Mode 5, a review of inservice inspection (ISI) results for activities performed during the second refueling outage in 1989 concluded that American Society of Mechanical Engineers (ASME)Section XI required exams had not been performed on some Service Water System (SWS) supports.

Section XI of the ASME Code, Article IWF-2420, " Successive inspection Intervals," states, "when a component support requires corrective measures.. that support shall be re-examined during the next inspection period.." During the 1989 r; fueling outage, a component support (3-SWP-6-PSR235) was examined and required corrective measures. However, a successivs exam was not performed for this support as required during the second period of the inspection interval.

During the 1989 refueling outage, component support 3-SWP-4-P5R126 was examined as an additional examination end required corrective measures.Section XI, Article IWF-2430, " Additional Examinations," part (a) specifies that "when tha results of examinations require corrective measures.. the component supports immediately adjacent to those r: quiring corrective action shall be examined. Also, the examinations shall be extended to include additional supports e

equalin number and similar in type, design, and function to those initially examined during the inspection." Part (b) specifies that "when these additional examinations require corrective measures.. the remaining component supports within the system of the same type, de.kn, and function shall be examined." Additional SWS component supports were examined at the time. Of these additim supports, some required corrective measures and, as a result, additional inspections were required of the total p,2ulation of SWS component supports.

Of the total population of SWS component supports, twenty-five (25) supports were located in areas where performance of the examinations to meet the code requirements were deemed impractical. 10CFR50.55a provides for relief, when justified, in these instances. However, relief was not specifically requested to allow excluding the examination of these component supports.

Technical Specification (TS) Surveillance Requirement 4.0.5 requires, in part, that examinations "be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code

• Failure to perform these examinations, is r: portable pursuant to 10CFR50.73(a)(2)(i)(B), as a condition prohibited by the Technical Specifications.

II.

Cause of Event

The apparent cause of this event was an inappropriate decision regarding the classification of these component supports as inaccessible and subsequent failure to apply for relief from these inspections. No documentation of the circumstances and decisions reached are available conceming the impracticality of the inspections or requests for relief.

A contributing factor would be that insufficient guidance was provided within the ISI program regarding the scheduling of additional or successive examinations, or requesting relief wh( ) the examinations were deemed impractical.

111. Analysis of Event Th3 condition is significant because of the operation in a condition prohibited by the Technical Specifications. However, th:re were no safety consequences due to the event since the twenty five Service Water System component supports f

considered inaccessible, when subsequently inspected, were determined to be acceptable.k f

.U.s. NUCLEAR REGULATORY Commission (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1)

DOCKET NUMBER (2)

LER NUMBER (6)

PAGE (3)

YEAR SEQUENTIAL REVISloN Millstone Nuclear Power Station Unit 3 05000423 NUMBER NUMBER 3 of 3 97 026 00 TEXT (If more space is required. use additionalcopies of NRC form 366A) (17)

Section XI Code Interpretation XI-1-86-30R issued on March 8,1995, states that when a component support has been analyzed to substantiate its integrity for its intended service and has been found to be acceptable additional sxaminations required by IWF-2430 and successive examinations required by IWF-2420 would not be required.

Although this interpretation was not available at the time of the event, it would not require that the additional and j

successive examinations be performed if this event occurred today.

l l

l l

IV. Corrective Action

The Section XI required additional and successive examinations have been performed sucessfully.

The following corrective actions will be taken:

1.

The ISI program documents will be revised to include guidance on the ASME Section XI requirements for performing additional and successive exams by June 30,1997.

2.

The ISI program documents will be revised to include guidance on the requirements for requesting relief in accordance with 10 CFR 50.55a by June 30,1997.

V.

Additional Information

None

Similar Events

None Manufacturer Data Ells System Code Essential Service Water System..

...Bl Nonessential Service Water System.

...KG Ells Component Code Su pport.....................................................SPT