05000423/LER-1996-032-01, :on 960910,HPSI Rv Piping Hydrostatic Test Was Found to Be non-compliance W/Asme Code Due to Personnel Error.Performed Test at Required Test Frequency

:on 960910,HPSI Rv Piping Hydrostatic Test Was Found to Be non-compliance W/Asme Code Due to Personnel Error.Performed Test at Required Test Frequency

ML20128M577
Person / Time
Site:	Millstone
Issue date:	10/09/1996
From:	Laudenat R NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20128M538	List: 05000423/LER-1996-032, Forwards LER 96-032-00 Re 960909 Event.Listed Commitments Will Be Completed Including Performance of Hydrostatic Test of Sih Relief Valves 05000423/LER-1996-032-01, :on 960910,HPSI Rv Piping Hydrostatic Test Was Found to Be non-compliance W/Asme Code Due to Personnel Error.Performed Test at Required Test Frequency
References
LER-96-032-01, LER-96-32-1, NUDOCS 9610160119
Download: ML20128M577 (3)

LER-1996-032, on 960910,HPSI Rv Piping Hydrostatic Test Was Found to Be non-compliance W/Asme Code Due to Personnel Error.Performed Test at Required Test Frequency

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
4231996032R01 - NRC Website

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NRC FORM 356 U.s. NUCLEAR REGULATORY COMMisslON APPROVED SY OM8 NO. 3150 0104 i

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FACadTY NAME W DOCKET NUM8ER (2)

PAGE13) i Millstone Nuclear Power Station Unit 3 05000423 1 of 3 TITLE I4)

High Pressure Safety injection Relief Valve Piping Hydostatic Test Non-compliance with ASME Code Due to Personnel Error EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEQUENTIAL Revision MONTH DAY YEAR FAclWTY NAME DOCKET NUMBER NUMBER l

09 10 96 96 032 96 10 09 96 i

OPERATING THis REPORT IS SUBMITTED PURSUANT To THE REQUIREMENTS OF 10 CFR 5: (Check one or more) (11)

MODE (M 6

20.22o1(b) 20.2203(a)(2)(v)

X so.73(a)(2)ii) 50.73(ali2)(viil)

POWER 20.22o3(a)(1) 20.2203(a)(3)(i)

So.73(a)(2)(ii) 50.73(a)(2)(x)

LEVEL (10) 000 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(iii) 73.71 20.22o3(a)(2)(ii) 20.2203(a)(4)

So.73(a)(2)(iv)

OTHER Mi 20.2203(a)(2)(iii) 50.36(c)(1)

So.73(a)(2)(v)

Sogc{ygA r t elow 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii)

LICENSEE CONTACT FOR THis LER (12)

NAME TELEPHONE NUMBER Onclude Area Code)

R. T. Laudenat, Nuclear Licensing Supervisor (860)444-5248 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) d

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPROS SUPPLEMENTAL REPORT EXPECTED (14)

EXPECTED MONTH DAY YEAR Submission g

YES No (If yes, complete EXPECTED sVBMisslON DATE).

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

On September 9,1996, with the plant in Mode 5, it was determined that a hydrostatic test of High Pressure Safety injection (SlH) piping that was not performed in accordance with the ASME Code Section XI was a non-compliance with Technical Specifications. The test was performed on September 13,1993 was performed above the system design pressure, but below the ASME Code pressure test requirements.

Th3 requirement for a hydrostatic test was the result of a design change that increased the rated pressure of a section of the SlH system. The correct test pressure, as required by the ASME Code, was a factor of 1.25 times the system pressure.

The test was performed at a factor of 1.1 times system pressure due to personnel error.

This condition is reported pursuant to 10CFR50.73(a)(2)(i)(B), as a noncompliance with Technical Specification 4.0.5. The requirements for pressure testing these components to Section XI of the ASME code are delineated in Technical Specification 4.0.5. The deviation from the test pressure required by Section XI of the ASME code is a non-conformance with the Technical Specification.

Th3 corrective action will be to perform the test at the required test pressure. The retest will be scheduled during the current outage. Additionally, retraining and counseling will be provided to the individuals responsible fm this event. Such r training will encompass ASME code requirements and system design requirements.

NRC FORM 366 (4-951 9610160119 961007 PDR ADOCK 05000423 g

PDR

NRC PORM 366A U.S. NUCLEAR REGULATORY CoMMtssioN (4 95)

UCENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1)

DOCKET NUMBER (2)

LER NUMBER (6)

PAGE (3)

YEAR SEQUENTIAL REVistoN Millstone Nuclear Power Station Unit 3 05000423 NUMBER NUMBER 2 of 3 96 032 96 TEXT (11more space is required, use additional copies of NRC Form 366A) t11) 1.

Descriotion of Event On September 9,1996, with the plant in Mode 5, while resolving an NRC Inspector's question it was determined that a prcssure test that had not been performed in accordance with the Section XI of the ASME code was a non-compliance with Technical Specifications. The test involved was a system hydrostatic test of the High Pressure Safety injection (SlH) piping, performed on September 13,1993. The requirement for a hydrostatic test was the result of a design change that increased the rated pressure of section of the SlH system. The hydrostatic test was performed above the system design pressure, but below the ASME code pressure test requirements.

Th3 ASME section XI 1983 edition, S83 addenda, Section IWC-5222, specifies that a system hydrostatic test pressure shall be at least 1.10 times the system design pressure for systems with a design temperature of 200 degrees Fchrenheit ( F) or less; and at least 1.25 times the system pressure for systems with a design temperature above 200 F. The hydrostatic test done under an ASME XI Repair / Replacement Plan, was performed at a factor of 1.1 versus th3 correct factor of 1.25. The event had no safety consequence. The test performed was successful and was above the system design pressure.

II.

Cause of Event

The cause of this event was personnel error. The personnel responsible for delineating the test requirements were aware of the hydrostatic testing requirements referenced in the appropriate goveming documents. When the repair / replacement (R/R) plan was developed to implement those requirements, the individual filling out the retest portion of the plan assumed the design temperature to be less than 200 F. This led to the discrepancy in the hydrostatic pressure test package. A note of caution from the American Nuclear insurance Inspector (ANil), during their review of the R/R plan, was not acted upon by the individual performing the testing. This is believed to be an isolated incident. A check with the site ANIl confirmed that this was the only R/R package that had this type of discrepancy noted during their review lll, Analysis of Event This condition is reported under 10CFR50.73(a)(2)(i)(B), as a noncompliance with Technical Specification 4.0.5.

Technical Specification 4.0.5 requires, in part, that examinations shall, "be performed in accordance with ASME Section XI of the ASME Boiler and Pressure Vessel Code.. except where specific relief has been granted by the Commission.

• The deviation from the test pressure required under Section XI of the ASME code is a non-compliance with the Technical Specification.

Th3 plants'"ASME Section XI Repair / Replacement Plans" are designed to implement the code required examinations as part of a repair, replacement or modification. The utilization of incorrect information in this test package to use a 1.1 factor for c.ietermining the appropriate test pressure caused the work orders to the field to be incorrectly prepared.

Hence, the retest did not meet the ASME Code. The event had no safety consequence. The test performed was successful and was above the system design pressure.

IV. Corrective Action

The corrective action will be to perform the test at the required test pressure. The retest will be scheduled during the current outage. Due to reorganizations, subsequent to this event, the responsible individuals have been re-assigned e

NRC PORM 366A 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 96 032 96 l

TEXT (11more space is required, use additional copies of NRC Form 366A) till or terminated. Counseling on this event and ASME code requirements for individuals currently assigned these functions has been completed.

V.

Additional Information

Similar Events None Manufacturer Data Ells System Code High Pressure Safety injection System - BQ l