05000155/LER-1997-001, :on 970102,containment Sphere Integrated Leakage Rate Test Was Not Performed IAW App J to 10CFR50. Caused Because TV-02 Did Not Provide Adequate Guidance for Control of Test.Blind Flange Was Removed
| ML20134D889 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/31/1997 |
| From: | Bourassa M, Donnelly P CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-97-001, LER-97-1, NUDOCS 9702050431 | |
| Download: ML20134D889 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii) 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 |
| 1551997001R00 - NRC Website | |
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Consumers POW 8f p. men u oonn,ny Plant Afanager POWERING nlKNoGAN'S PROGRESS Big Rock Posnt Nuclear Plant,10269 US-31 North, Charlevoia. MI 49720 January 31, 1997 i
Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - LICENSEE EVENT REPORT 97-001: TEST NOT PERFORNED IN ACCORDANCE WITH APPENDIX J TO 10 CFR PART 50.
Licensee Event Report 97-001, TEST NOT PERFORNED IN ACCORDANCE WITH APPENDIX J TO 10 CFR PART 50, is attached. This event is reportable to the Nuclear Regulatory Commission in accordance with 10 CFR 50.73(a)(2)(1) - Any operation prohibited by the plant's technical specifications A/8 n
Patrick M Donnelly Plant Manager CC: Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point l
ATTACHMENT f
i 9702050431 970131 PDR ADOCK 05000155 S
PDR 050000 q[
A C&G ENERGYCOMPANY
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Consumers power p.,,ic, u oonn.i,,
Plant Munarer POWERING i
nlKHNEAN5 PRENiRE55 Big Rock Pomt Nuclear Plant.10269 US 31 North. Charlevoin MI 49720 1
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January 31, 1997 i
Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - LICENSEE EVENT REPORT 97-001: TEST NOT PERFORNED IN ACCORDANCE WITH APPENDIX J TO 10 CFR PART 50.
Licensee Event Report 97-0D1, TEST NOT PERFORNED IN ACCORDANCE WITH APPENDIX J TO 10 CFR PART 50, is attached. This event is reportable to the Nuclear Regulatory Commission in accordance with 10 CFR 50.73(a)(2)(i) - Any operation prohibited by the plant's technical specifications Patrick M Donnelly (Signed)
Patrick M Donnelly Plant Manager CC: Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point ATTACHMENT A C46 ENE7?GYCOMPANY
. NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104
'4445)
EXPIRES 04/30/98
' EATSONIEEcT o REEEEnoEIRUEETIo"tEsEO sLURNE E
LICENSEE EVENT REPORT (LER)
INCORPORATED INTo THE UCENSING PROCESS AND FED SACK TO INDUSTRY.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION A@
(Sea reverse for required number of RE m Ds NAGE NT BA S F33 US NUCLEAR REQULATORY digits / characters for each block)
REDUCTION PROJECT (3150o104). OFFICE OF MANAGEMENT AND SUDGET.
W ASHINGTON, DC 20603 4
FOC117Y NAME (11 DOCKET NUMBER (2)
PAGE (3)
HBIG ROCK POINT NUCLEAR PLANT 50-155 1
0F 3
l TITLE K$
l Test Not Performed in Accordance With Appendix J to 10 CFR Part 50.
l EVENT DATE (5) l LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR MONTH DAY YEAR l
l1 2
97 l 97 001 00 1
31 97 l
OPERATING l THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 1: (Check one or more) (11)
N j
MODE (9) l l
20.2201(b) 20.2203(a)(2)(v)
X 50.73(a)(2)(i) 50.73(a)(2)(viii)
POWER 0%
LElfEL (10) 20.2203(a)(2)(il 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 Abstract below or 20.2203(a)(2)(iv) 50.36(c)(2) 50.73(a)(2)(vii) in NRC Form 366A j
LICENSEE CONTACT FOR THIS LER (12) j
._.. _ ~.... _.. _.. _.. _.
musum NAME TELEPHONE NUMBER (INCLUDE AREA CODO HMichael D. Bourassa, Licensing Supervisor 1-616-547-8244 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CausE
SYSTEM COMPONENT MANUFACTURER
CAUSE
SYSTEM COMFONENT MANUFACTURER RPD D
BD NA NA N
SUPPLEMENTAL REPORT EXPECTED (14)
MONTH DAY YEAR NO NM f es, complete EXPECTED SUBMISSION DATE).
l ABSTRACT (Limit to 1400 spaces,i.e., approximately 15 single-spaced typewritten lines) (16)
Big Rock Point Technical Specification 3.7(d) requires that " containment sphere integrated leakage rate tests (Type A, B, and C) shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR Part 50, as modified by approved exemptions".
On January 2,1997, at 1948 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.41214e-4 months <br />, plant procedure TV-02, Containment Integrated Leak Rate Test (ILRT), was initiated. The purpose of this procedure is to pressurize the containment sphere through penetration H-80 and its associated containment isolation valve VCI-1, then measure leakage after 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. When the air compressors were valved in to supply air into the containment sphere, and the test could not be performed as expected, the engineers determined that a blind flange had been installed between system piping flanges.
The blind flange is believed to have been in this location since 1992, the date of the last ILRT. This condition is contrary to Big Rock Point Technical Specification 3.7(d) because any Local Leak Rate Tests (LLRTs) conducted on this penetration since 1992 were not performed in accordance with Appendix J criteria.
1 The root cause concluded that TV-02 did not provide adequate guidance for the control of this test. TV-02 will be revised to address the use of the blind flange.
NRCCORM 366(4-95)
.U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1)
DOCKET LER NUMBER (6)
PAGE (3) escuewriAL newesoN Big Rock Point Nuclear Plant 50-155 2 0F 3 97 001 00 TEXT (W more space in required, une eMtional copies of NRC Form 366A) (17)
IDENTIFICATION OF EVENT This event is reportable to the Nuclear Regulatory Commission pursuant to :
10 CFR 50.73(a)(2)(1)(B)
"Any operation prohibited by the plant's Technical Specifications".
REFERENCES
- 1. Big Rock Point Technical Specification 3.7(d).
- 3. LER 96-013 Automatic Reactor Scram Initiated by Turbine.
- 4. TV-02, Containment Integrated Leak Rate Test (ILRT).
- 5. 10 CFR 50 Appendix J-Frimary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.
EVENT DESCRIPTION
On January 2, 1997, at 1948 hours0.0225 days <br />0.541 hours <br />0.00322 weeks <br />7.41214e-4 months <br />, TV-02, was initiated. The purpose of this procedure is to pressurize the containment sphere [NH] through penetration [ PEN] H-80 and the associated containment isolation valve VCI-1 [ISV], then measure leakage after 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
l When the air compressors were valved in to supply air into the containment sphere, and the I
test could not be performed as expected, the engineers determined that a blind flange had been installed between system piping flanges. The blind flange is believed to have been i
in this location since 1992, the date of the last ILRT. This condition is contrary to Big Rock Point Technical Specification 3.7(d) because four Local Leak Rate Tests (LLRTs) conducted on this penetration since 1992 were not performed in accordance with Appendix J criteria. The H-80 containment penetration was tested in this condition and no leakage requirements were exceeded. However piping downstream of VCI-l was not properly vented, therefore the normally closed VCI-1 was not tested in accordance with Appendix J requirements.
ROOT CAUSE A root cause analysis was performed and concluded that an inadequate procedure precipitated the event. The procedure does not provide the appropriate amount of detail for the outboard blind flange installation, which can lead to a nonconforming test.
..U.S. NUCLEAR REGULATORY COMMISSION 4440 LICENSEE EVENT REPORT (LER) i TEXT CONTINUATION FACILITY NAME (1)
DOCKET LER NUMBER (6)
PAGE (3)
MOUENTIAL REVIS60N g
Big Rock Point Nuclear Plant 50-155 3 0F 3 97 001 00 TEXT (11more space is required, use additional copies of NRC Form 366A) (17)
CORRECTIVE ACTION
Immediate The blind flange was removed, a new gasket was inserted, a successful LLRT was performed on H-80, and containment sphere pressurization resumed.
, Long Term Station procedure TV-02, Containment Integrated Leak Rate Test (ILRT), will be revised to provide direction with respect to the outboard blind flange on containment penetration H-j 80.
THIS ACTION WILL BE COMPLETED BY MAY 1, 1997
SAFETY SIGNIFICANCE
This event had no safety significance since containment integrity leakage requirements have been maintained. There have been four successful local leak rate tests (since the 1992 ILRT) on penetration H-80. With the blind flange installed, (see Figure 1), VCI-1 is not vented downstream as required by Appendix J. However, the measured leakage from H-80 in this configuration (testing the blind flange instead of VCI-1) did not affect the containment leak rate summary results. Therefore, while the LLRTs were not performed in accordance with approved testing methods with respect to VCI-1, containment penetration leakage requirements have been satisfied (as demonstrated by the four successful LLRT since 1992), remaining below the Appendix J acceptance criteria.
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