05000261/LER-2004-002, Entry Into Mode 3 with the Steam Driven Auxiliary Feedwater Pump Flowpath Inoperable

Entry Into Mode 3 with the Steam Driven Auxiliary Feedwater Pump Flowpath Inoperable

ML042050202
Person / Time
Site:	Robinson
Issue date:	07/21/2004
From:	Clearly T Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/04-0096 LER 04-002-00
Download: ML042050202 (6)

LER-2004-002, Entry Into Mode 3 with the Steam Driven Auxiliary Feedwater Pump Flowpath Inoperable

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(B)
2612004002R00 - NRC Website

text

10 CFR 50.73 8J Progress Energy Serial: RNP-RA/04-0096 JUL 2 1 2004 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 LICENSEE EVENT REPORT NO. 2004-002-00 ENTRY INTO MODE 3 WITH THE STEAM DRIVEN AUXILIARY FEEDWATER PUMP FLOWPATH INOPERABLE Ladies and Gentlemen:

The attached Licensee Event Report is submitted in accordance with the requirements of 10 CFR 50.73. Should you have any questions regarding this matter, please contact Mr. C. T. Baucom, Supervisor - Licensing/Regulatory Programs, at (843) 857-1253.

Sincerely, Timothy P. Cleary Plant General Manager H. B. Robinson Steam Electric Plant, Unit No. 2 CTB/cac Attachment c:

Dr. W. D. Travers, NRC, Region II Mr. C. P. Patel, NRC, NRR NRC Resident Inspector, HBRSEP Progress Energy Carolinas, Inc.

Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550 i52vS

NRC F6RM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004 r7-2001)

COMMISSION

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

FACILITY NAME (1)

DOCKET NUMBER (2)

PAGE (3)

H. B. Robinson Steam Electric Plant, Unit No. 2 05000261 1 OF 5

TITLE (4)

Entry into MODE 3 with the Steam Driven Auxiliary Feedwater Pump Flowpath Inoperable EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED (8)

FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR SEQUENTIALI REV MO DAY YEAR FACILITY NAME DOCKET NUMBER 05 23 2004 2004 - 002 - 00 07 21 2004 _

OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THIE REOUIREMENTS OF 10 CFR.

(Check all that apply) (1 1)

MODE (9) 3 20.2201 (b)

_ 20.2203(a)(3)(ii)

_ 50.73(a)(2)(ii)(B)

_ 50.73(a)(2)(ix)(A)

POWER 20.2201 (d) 20.2203(a)(4) 50.73(a) (2) (iii) 50.73(a)(2)(x)

LEVEL (10) 0%

20.2203(a)(1) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71 (a)(5) 20.2203(a)(2)(ii) 50.36(c)(2) 50.73(a)(2)(v)(B)

OTHER

- Specify in Abstract below or in 20.2203(a)(2)(iii) 50.46(a)(3)(ii)

_50.73(a)(2)(v)(C)

NRC Fr A

20.2203(a)(2)(iv) 50.73(a)(2)(i)(A)

_50.73(a)(2)(v)(D) 20.2203(a)(2)(v)

X 50.73(a)(2)(i)(B) 50.73(a)(2)(vii)

]

20.2203(a)(2)(vi)

_ 50.73(a)(2)(i)(C) 50.73(a)(2)(viii)(A) 20.2203(a)(3)(i)

_ 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(B)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Include Area Code)

C. T. Baucom I

843-857-1253 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE

SYSTEM COMPONENT l MANU-l REPORTABLE

- l

CAUSE

SYSTEM l COMPONENT MANU-REPORTABLE CURER TO EPIX FCTURER TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)

DAYSUBMISSION M

D YEAR YES (If yes, complete EXPECTED SUBMISSION DATE).

X NO DATE (15) l l

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

At 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br /> on May 23, 2004, during operations being conducted for restart of H. B. Robinson Steam Electric Plant CHBRSEP). Unit No. 2, the reactor operating MODE was changed from MODE 4 to MODE 3 with the Steam Driven Auxiliary Feedwater (AFW) pump flowpath not correctly aligned for operation, as required by Section 3.7.4 of the HBRSEP, Unit No. 2, Technical Specifications.

Specifically, the suction valve (AFW-4) to the Steam Driven AFW pump was closed with a caution tag that stated the valve was to be maintained in the "closed' position. At 2139 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.138895e-4 months <br />, the caution tag was removed and the suction valve was opened. Opening the suction valve restored compliance with the Technical Specifications requirement in Section 3.7.4, as delineated in Surveillance Requirement 3.7.4.1, which requires each AFW valve in each water flowpath to be in the correct position.

It was determined that the root cause of this situation was conflicting requirements. Corrective actions to revise the appropriate procedures are planned that will improve the procedural guidance and prevent recurrence of this situation. The health and safety of the public and plant personnel were not impacted by this event. The required safety functions were maintained, and the operating parameters of the plant were maintained within required safety limits. The condition described in this Licensee Event Report is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as any operation or condition which was prohibited by the plant's Technical Specifications.

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u I,-c.J rIrt rur- -%I t-WI (If more space Is required, use additional copies of (If more space Is required, use additional copies of (if more space Is required, use additional copies of (If more space Is required, use additional copies of NRC Form 366A) (17)

• Revise operations procedures to ensure review of caution tags, temporary modifications, and equipment inoperability records prior to crossing into MODE 5, 4, 3, or 2. This action is planned for completion by September 16, 2004.

V.

ADDITIONAL INFORMATION

A. Failed Component Information:

No components were considered to have failed during this event. As previously stated, the leakage associated with the steam admission valve was not directly related to the improper alignment of the Steam Driven AFW pump flowpath. The subsequent discovery of inoperability of the Steam Driven AFW pump was also a separate condition that is not directly related to the improper alignment of the Steam Driven AFW pump flowpath.

B. Previous Similar Events

A review was performed for similar events at HBRSEP, Unit No. 2, where a MODE change was not performed in accordance with the requirements of LCO 3.0.4 due to equipment misalignment.

No recent events of this type were identified.