05000423/LER-1996-050-01, :on 961211,chill Water Pump Suction Pressure Gauges (3HVK-P126A & 3HVK-P126B) Did Not Meet Instrument Range Requirements.Caused by Inadequate Administrative Structure for IST Program.Procedure Change Implemented

:on 961211,chill Water Pump Suction Pressure Gauges (3HVK-P126A & 3HVK-P126B) Did Not Meet Instrument Range Requirements.Caused by Inadequate Administrative Structure for IST Program.Procedure Change Implemented

ML20133F142
Person / Time
Site:	Millstone
Issue date:	01/10/1997
From:	Peschel J NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20133F115	List: 05000423/LER-1996-050-01, :on 961211,chill Water Pump Suction Pressure Gauges (3HVK-P126A & 3HVK-P126B) Did Not Meet Instrument Range Requirements.Caused by Inadequate Administrative Structure for IST Program.Procedure Change Implemented
References
LER-96-050-01, LER-96-50-1, NUDOCS 9701140081
Download: ML20133F142 (3)

LER-1996-050, on 961211,chill Water Pump Suction Pressure Gauges (3HVK-P126A & 3HVK-P126B) Did Not Meet Instrument Range Requirements.Caused by Inadequate Administrative Structure for IST Program.Procedure Change Implemented

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
4231996050R01 - NRC Website

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8 RC FORM 336 U.s. NUCLEAR REGULATORY COMMisslON APPROVED BY OMS NO. 3150-0104 (4-95)

EXPIPES 04/30/98 kO TO cot. LECT RE UE S 60 hrs EPO TED x-EcI"'?o^"AoTTn7 "*Plaf.'no'"odSWnIS20'u'3^2n!M LICENSEE EVENT REPORT (LER) 15m^U 2 'a'N!""#o%%a'88"oa "s^J,P'".'s"%^n" R n a u fo = l e " = u '. = s u an' a r "

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FCcluTY NAME 111 DOCKET NUMBER (2)

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Millstone Nuclear Power Station Unit 3 05000423 1 of 3 TITLE 14) i Range Of Control Building Chilled Water Pump Suction Pressure Gauges Used For Surveillance Not In Accordance With ASME Chapter XI Requirements EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEQUENTIAL REVislON MONTH DAY YEAR FAcluTY NAME DOCKET NUMBER NUMBER 1

12 11 96 96 050 00 01 10 97 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check one or more) (11)

MODE (9) 5 20.2201(b) 20.2203(a)(2)(v)

X So 73(a)(2)(i)

So.73(a)(2)iviii)

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

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

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LEVEL (to) 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)

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OTHER qM 20.22o3(a)(2)(iii)

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SpecifY in Abstract below Mn.2 g@ s.

or m NRC Form 366A LICENSEE CONTACT FOR THIS LER (12)

NOME TELEPHONE NUMBER Unclude Area Codel J.M. Peschel, MP3 Nuclear Licensing Manager (860)437-5840 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE

CAUSE

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

EXPECTED MONTH DAY YEAR SU8MSSION

[ NO YES (if yes, complete EXPECTED sUBMisslON DATE).

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

On December 11,1996, with the plant in Mode 5, it was determined that the Chill Water Pump suction pressure gauges (3HVK-Pl26A and 3HVK-Pl26B) did not meet the instrument range requirements imposed by Section XI of the Code of the American Society of Mechanical Engineers (ASME), " Rules for Inservice inspection of Nuclear Power Plant Components".

ASME Section XI requires that the full range of each analog instrument shall not be greater than three times the reference value. The reference value of the Control Building Chill Water pumps suction pressure gauges is 8.7 pounds per square inch gauge (psig) during the pump operational readiness test. Therefore, the full range of the gauges should be less than 26.1 psig. The range of the currently installed analog gauges used to determine the operability of the Control Building Chill Water Pumps (3HVK*P1 A/B) is 0 to 30 psig. The event is being reported pursuant to 10CFR50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.

The safety significance and consequence of this event are minimalin that a review of the installed Chill Water Pump suction pressure gauges determined that they met the accuracy requiremems of ASME Section XI. Furthermore, the hydraulic performance of both pumps was reviewed, and the pumps were determined to be operable. As a result, both pumps would have been capable of meeting their specified safety function if called on to do so.

A procedure change will be implemented that utilizes a digital plant process computer read-out in lieu of the Chill Water Pump suction pressure analog gauges. The digital computer point meets the range and accuracy requirements of ASME Operations and Maintenance (O&M) guideline #6.

9701140081 970110 PDR ADOCK 05000423 S

PDR

3U.s. NUCLEAR REGULATORY Commission (4 95)

UCENSEE 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 2 of 3 96 050 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) 1.

Description of Event

On December 11,1996, with the plant in Mode 5, it was determined that the Chill Water Pump suction pressure gauges (3HVK-Pl26A and 3HVK-Pl268) did not meet the instrument range requirements imposed by Section XI of the Code of the American Society of Mechanical Engineers (ASME)," Rules for Inservice Inspection of Nuclear Power Plant Components". ASME Section XI requires that the full range of each analog instrument shall not be greater than three times the reference value. The reference value of the Control Building Chill Water pumps suction pressure gauges is 8.7 pounds per square inch (psig) during the pump operational readiness test. Therefore, the full range of the gauges should be less than 26.1 psig. The range of the currently installed analog gauges used to datermine the operability of the Control Building Chill Water Pumps (3HVK*P1 A/B) is 0 to 30 psig.

Technical Specification 4.0.5 requires that the Inservice Test (IST) program be performed in accordance with the requirements of ASME Section XI. Pursuant to 10CFR50.55a(g)(6)(i), exemptions to the IST program and alternate testing method requests must be submitted to the NRC for approval.

The program to meet the requirements of ASME Section XI is delineated in the IST Program Manual. The instrument range of the installed analog gauges does not meet the requirements contained within the IST Program Manual. The IST Program Manual does not identify the above gauges as deviating from the requirements of ASME Section XI, and a relief request was not submitted to use the existing pressure gauges. Consequently, the previously performed inservice tests do not meet the Technical Specifications surveillance requirement due to the range of the instrumentation used.

This problem was originally discovered in 1993. A Plant Modification Request (PMR) was generated on July 20, 1993 to replace the gages with ones having a narrower range to satisfy ASME section XI requirements. On November 29,1994, the PMR was disapproved and canceled as the existing gauges were deemed acceptable at that time. The inappropriate resolution was identified while performing an evaluation of the inservice Test (IST) program for design bases compliance.

The event is being reported pursuant to 10CFR50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.

II,

Cause of Event

The cause for the 3HVK-Pl26A/B gages not complying with the requirements contained within Technical Specifications was an inadequate administretive structure for the IST program. There were no requirements for periodic program reviews nor was there guidance on documenting and tracking of identified problems. These weaknesses in the program allowed the problem to go undetected from plant startup until 1993 and then allowed the problem to go uncorrected, after being identified, for three more years.

Ill. Analysis of Event The safety significance and consequence of this event are minimal in that a review of the installed Chill Water Pump suction pressure gauges determined that they met the accuracy requirements of ASME Section XI. As a result, both pumps would have been capable of meeting their specified safety function if called on to do so.

CRC FQRM 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 96 050 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) 4 4

IV. Corrective Action

Upon discovery of this discrepancy, a review of other gauges within the IST Program was initiated. This review will be completed, and discrepancies will be corrected prior to July,1997.

4 A procedure change will be implemented by February 1,1997 to substitute a digital plant process computer read-out in lieu of the Chill Water Pump suction pressure analog gauges. This digital read-out, with a calibrated range of 50 psig, will meet the ASME Operations and Maintenance (O&M) guideline #6 instrument range requirement that the reference value for digitalinstruments not exceed 70 percent (%) of the calibrated range of the instrument.

As previously reported in LER 96-021-01," Components Not included In The In-Service Test Proaram As A Result Of Proarammatic Deficiencies", a procedure will be implemented to administer and monitor the IST program by May 31, 1997.

t V.

Additional Information

None.

Similar Events

LER 96-021-01

" Components Not included in The in-Service Test Proaram As A Result Of Proarammatic Deficiencies

• On June 28,1996 with the unit in mode 5 of an extended cold shutdown, a review of the Inservice Test Program was completed. This review identified multiple Inservice Test (IST) Program deficiencies which consist of incomplete implementation of several licensing commitments, the omission of several valves from the program, testing inadequacies for valves already in the program, inconsistent or missing documentation in the Inservice T0ct Manual and IST surveillance procedures, and lack of adequate process control procedures which would ensure effective maintenance of the program.

The causes of this condition were a lack of management commitment to support these programs, inadequate program monitoring, and a failure to evaluate the program effectiveness. Correction of individual discrepancies and programmatic enhancements to prevent recurrence are being incorporated into the IST manual and applicable surveillance procedures.

Manufacturer Data Ells System Code:

Chill Water System-KM Ells Component Code:

Transmitter, Indicating, Pressure - PIT