05000315/LER-1998-058, :on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122

:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122

ML17335A414
Person / Time
Site:	Cook
Issue date:	12/16/1998
From:	Gebbie J INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17335A413	List: 05000315/LER-1998-058, :on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
References
LER-98-058, LER-98-58, NUDOCS 9812230138
Download: ML17335A414 (5)

LER-1998-058, on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(x) 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)(ii)(B), Unanalyzed Condition
3151998058R00 - NRC Website

text

NRC Form 366 U.S. NUCLEAR EGULATORYCOMMISSION (6-1998)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY OMB No. 3150.0104 EXPIRES 06)30/2001 ESTSIATED BURDEN PER

RESPONSE

TO COMPLY WITH THIS MANDATORY WFORMATIONCOILECTION REOVEST: 50 0 HRS. REPORTED LESSONS LEARNEDARE INCORPORATED WTO THE UCENSING PROCESS AND FED BACK TO WDUSTRY.

FORWARD COMMENTS REGARDWG BURDEN ESTIMATE TO THE INFORMATIONAND RECORDS MANAGEMENT BRANCH (T4 F55).

U.S.

NUCLEAR REGIRATORY COMMISSIILWAQ40ATOIL DC 205554001. AND TO THE PAPERWOIW REDVCTION PROJECT (51504104),

OFFICE OF MANAGEMENT AND BVDGET, WASICNGTOIL DC 20505 FACIUTYNAME(1)

TITLE(4)

Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 05000-315 PAGE (5) 1 of3 Postulated High Energy Line Break Could Result in Condition Outside Design Bases for Auxiliary Feedwater EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIESINVOLVED(8)

MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REVISION NUMBER MONTH DAY YEAR ILI NAM DC Cook - Unit 2 NUM R

05000-316 16 1998 1998

058 00 12 16 1998 ILI C

NVM OPERATING MODE (9)

POWER LEVEL(10) 000 20.2201 (b) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(v) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(viii) 50.73(a)(2)(x) 73.71 THIS REPORT IS SUBMITTEDPURSUANT TO THE REQUIREMENTS OF 10 CFR g: (Check one or more) (11) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)

LICENSEE CONTACT FOR THIS LER (12) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii)

OTHER Specify IrrAb51racI behw or nNRCFcnn366A Mr. Joel Gebbie, Safety Related Mechanical Engineering Supervisor TELEPHONE NUMBER(Inrdvde Area Code) 616/465-5901 x1543 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX

$ 51'

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX SUPPLEMENTAL REPORT EXPECTED (14 X

YES (IfYes, complete EXPECTED SUBMISSION DATE NO EXPECTED SUBMISSION DATE 15)

MONTH 02 OAY

. 08 1999 Abstract (Limitto 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

During a Safety System Functional Inspection (SSFI) self-assessment of the Auxiliary Feedwater (AFW) System, a request was made to review the High Energy Line Break (HELB) analysis for the AFW pump common hallway. The Unit 1 East Motor Driven Auxiliary Feedwater Pump (MDAFP), Unit 1 Turbine Driven AuxiliaryFeedwater Pump (TDAFP), Unit 2-East MDAFP, and Unit 2 TDAFP are located adjacent to each other and share a common hallway. A HELB analysis for the hallway could not be located.

Evaluation of the potential effects of a HELB on the AFWpumps resulted in the conclusion that this condition could lead to the concurrent failure of the TDAFP and a single MDAFP. On November 16, 1998 this condition was determined to be reportable.

Therefore, this LER is being submitted in accordance with 10 CFR 50.73 (a)(2)(ii)(B) as a condition outside the design bases of the plant.

The root cause of this condition was determined to be deficiencies associated with the administration of the HELB program. An independent assessment of the program has been completed, which identified several programmatic deficiencies.

These deficiencies are being addressed in the aggregate, and corrective actions to address the programmatic deficiencies willbe available in early February 1999.

Engineering personnel willperform a HELB analysis of the AFW System and perform necessary actions to restore the system to its design bases.

The safety significance of this condition was evaluated considering the loss of both the TDAFP and a single MDAFP on a HELB in the area.

Based on the fact that a single MDAFP can provide sufficient flow in order to safely shut down the plant and one MDAFP would be unaffected by the HELB, itwas determined that the condition did not pose a threat to the health or safety of the public.

'2)812230138 981 216 PDR ADQCK 05000315 8

PDRU.S. NUCLEAR REGULATORY COMMISSION (6-1998)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITYNAME(1)

Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 05000-315 YEAR 1998 LER NUMBER (6)

SEQUENTIAL NUMBER 058 REVISION NUMBER 00 PAGE (3) 2 of 3 TEXT (ifmore spece is required, use eddilionel copies ofNRC Form (366A) (17)

Conditions Prior to Event

Unit 1 was in Mode 5, Cold Shutdown Unit 2 was in Mode 5, Cold Shutdown Descri tion of Event On September 21, 1998, a Safety System Function Inspection (SSFI) self-assessment of the AuxiliaiyFeedwater (AFW) system began, using SSFI techniques in accordance with NRC Inspection Procedure 93801, "Safety System Functional Inspection". The inspection team utilized a vertical slice review in the functional areas of engineering design and configuration control, operations, maintenance, surveillance and testing, and quality assurance and corrective actions.

The self-assessment concluded on October 23, 1998.

During the SSFI, an inquiry was made to review the High Energy Line Break (HELB) analysis for the AFWpump common hallway. No such analysis could be located.

On November 16, 1998 it was determined that the potential effects of a HELB in the area was reportable in accordance with 10 CFR 50.73(a)(2)(ii)(B) as a condition outside the design bases of the plant.

The Unit 1 East Motor Driven Auxiliary Feedwater Pump, Unit 1 Turbine Driven Auxiliary Feedwater Pump, Unit 2 East Motor Driven Auxiliary Feedwater Pump, and Unit 2 Turbine Driven Auxiliary Feedwater Pump are located adjacent to each other and share a common hallway. The steam used to drive the TDAFP turbines is provided by 4 inch supply lines, which tap offof the 30 inch Main Steam header.

Due to the 4 inch steam supply lines, it is possible for a HELB to occur in either of the TDAFP rooms. To help mitigate the consequences of the postulated break, the doors to the TDAFP rooms are propped open while the doors to the MDAFP rooms are maintained closed.

This arrangement allows the steam from the HELB to exhaust into the common hallway shared by the pumps.

Investigation has revealed that no analysis could be located which evaluated the effects of the HELB on the equipment in the common hallway. A line break in the area will result in a temperature of 330 F and a pressure of 14.7 psia, as indicated on plant drawing 1(2)-1355.

Four components were identified which may be rendered inoperable following a HELB. Those four components are

1. The cable which supplies power to 1-WMO-753, Essential Service Water Supply To The TDAFP The qualification report for the cable states that it can operate in an environment of 250 'F, 26.7 psia, and 100% relative humidity. Since the qualified temperature of the cable is less than the calculated temperature of 330 'F, it was assumed to fail.

2. The cable which supplies power to 1-WMO-754, Essential Service Water Supply To The East Motor Driven Auxiliary Feedwater Pump The qualification report for the cable states that it can operate in an environment of 250 'F, 26.7 psia, and 100% relative humidity. Since the qualified temperature of the cable is less than the calculated temperature of 330 'F, it was assumed to fail.

3. The cable which supplies power to 2-WMO-753, Essential Service Water Supply To The TDAFP The qualification report for the cable states that it can operate in an environment of 250 'F, 26.7 psia, and 100% relative humidity. Since the qualified temperature of the cable is less than the calculated temperature of 330 'F, it was assumed to fail.

4. The cable which supplies power to the solenoid for 2-FRV-258, TDAFP Emergency Leakoff Regulating Valve No qualification records could be located for the cable; therefore, itwas conservatively assumed that the valve would fail.

The electrical components listed above may not withstand the effects of the harsh steam-air environment.

Per Table 14.4.2-1 of the UFSAR, the four components are required for the safe shutdown of the plant. Therefore, it was concluded this condition could lead to the failure the TDAFP and a single MDAFP upon a HELB in the area.U.S. NUCLEAR REGULATORY COMMISSION (6-1998)

LICENSEE EVENT REPORT (LER)

. TEXT CONTINUATION.

FACILITYNAME (1)

Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 05000-315 YEAR LER NUMBER (6)

SEQUENTIAL NUMBER REVISION NUMBER PAGE (3) 3 of 3 1998 058

'0 TEXT (Ifmore space is required, use addilional copies ofNRC Form (366A) (17)

Cause of Event

The root cause of this condition is that the HELB program lacks a clearly defined, centralized owner.

It was determined that there is no central location for the HELB analyses that have been completed for the plant. The information is fragmented throughout the organization.

Also, there is no single authority responsible for the HELB program and much of the HELB program appears to be "tribal knowledge" held by different individuals throughout the organization.

In effect, the procedural controls for the HELB program are inadequate.

Anal sis of Event This LER is submitted in accordance with 10 CFR 50.73(a)(2)(ii)(B), as a condition outside the design bases of the plant.

The AFWsystem provides water to the steam generators when main feedwater is unavailable because of a loss of main feedwater, unit trip, feedwater or steam line break, loss of off-site power, or small break Loss of Coolant Accident (SBLOCA). This water removes core residual heat to prevent the release of primary water through the pressurizer safety or power-operated relief valves and allows the plant to cool down to the point at which Residual Heat Removal (RHR) can

' be placed in service.

Each unit is equipped with one turbine driven AFWpump and two motor driven AFW pumps.

For each unit, the TDAFP serves all four steam generators and each MDAFWpump serves two steam generators.

The steam to the AFW pump turbine is supplied from two of the steam generators.

The preferred source ofwater for the AFWsystem is the non-safety related CST. Each unit's CST is cross-tied by a normally closed air operated valve to provide condensate to the opposite unit's AFW. Ifboth CSTs are unavailable, water is supplied from Lake Michigan via the s'afety related ESW system, which is connected upstream of the AFW pump suction strainers.

A minimum of 175,000 gallons is required to maintain the unit at hot shutdown for nine hours.

A HELB in the area may lead to a concurrent failure of the TDAFP and a single MDAFP. As determined by the Appendix R

analyses, a single MDAFP, with a capacity of 450 gpm, can provide adequate cooling in order to safely shut down the unit.

The West MDAFP would not be affected. by a HELB in the area.

Therefore, it was concluded that this condition does not jeopardize health and safety of the public.

Corrective Actions

Engineering personnel willperform a HELB analysis of the AFWsystem and perform necessary actions to restore the Auxiliary Feedwater System to its design basis.

The HELB analysis of AFWwillbe completed by January 22, 1999. Ifany plant modifications are required as a result of the analysis, the modifications willbe completed prior to restart.

An independent assessment of the HELB program has been performed by an outside consultant.

Several programmatic deficiencies were identified during the assessment.

These deficiencies are being addressed in the aggregate, and corrective actions to address the programmatic deficiencies willbe available in early February 1999.

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