ML18348A210

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License Event Report 1977-047-00 Re Loss of Off-Site Power
ML18348A210
Person / Time
Site: Palisades Entergy icon.png
Issue date: 10/18/1977
From: Hoffman D
Consumers Power Co
To: James Keppler
NRC/RGN-III
References
LER 1977-047-00
Download: ML18348A210 (3)


Text

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consumers

  • Power company General Offices: 2*12 West Michigan Avenue, Jackson, Michigan 49201
  • Area Code 517 788-0550 October l8, 1977

~..r James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60l37 DOCKET 50-255 - LICENSE DPR PALISADES PLA.11T - ER-TT-047 -

LOSS OF OFF-SITE POWER

  • Attached is a 14-day reportable occurrence relating to the loss of off-site power at the Palisades Plant on September 2l+, 1977. The report due date was extended one week as previously discussed with Mr R Warnick.

P-~ attachment to the LER is provided for additional details.

David P Hoffman Assistant Nuclear Licensing Administrator CC: ASchwencer, USNRC OCT 2 o i977

  • ATTACHMENT TO LER 77-047 The cause of the 'R' Bus loss is not known. Loss of off-site power causes a loss of main condenser cooling water. Thus, the main turbine tripped on high back pressure and tripping of the main generator and reactor occurred. Both emergency diesel generators started immediately, loaded properly and performed satisfactorily throughout the incident. The secondary system was isolated, primary system stabilized and the plant functioned as designed during the incident.

Atmospheric dumps were operated as necessary to maintain PCS temperature. During the incident, power was lost to the Security System and extra Security personnel were called into the plant. Technical Specifications 3.1.1 and 3.7.1 were violated.

3.1.1 At least one primary coolant pump or shutdown cooling pump shall be in operation whenever a change is being made in the boron concentration of the primary coolant.

It is conservative and prudent to borate the plant to shutdown condition after a reactor trip. Boron samples during the incident and after restoring primary coolant flow were as anticipated and verified that no stratification occurred.

3.7.1 The primary coolant system shall not be heated above 325°F or maintained above 325°F if the following electrical systems are not operable.

a. Station power transformer 1-2 .
  • b.

1.

Start-up transformer 1-2.

2400 'V' Bus 1-E.

Throughout the incident the plant was maintained in hot shutdown. Power was restored after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 45 minutes. It was prudent to maintain the PCS hot rather than add to the Operators workload as power was restored shortly, and plant conditions were stabilized. This is permitted by C.E. Standard Technical Specifications. Changes to 3.1.1 and 3.7.1 will be submitted for approval.

The plant operated as analyzed and no failures of safety-related systems occurred as a result of this incident .

-.LICENSEE EVENT REPORT

  • Palisades CJJNTROL BLOCK :I....__.___._I__._I__._I__._I__.I (PLEASE PRINT ALL REQUIRED INFORMATION)

.1 6 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

@ill IM II Ip IA I L 1-1 I 10101-10101010101-10101 I 4 11

  • 11 11 11 *I 1°31 1132I 7 B 9 14 15 25 26 30 REPORT REPORT TYPE SOURCE COCK~ NUMBER EVENT CATE REPORT CATE 7

@El caN'T 8

r *1

  • 1 57 58 L!] ll:J IOl5IOl-IOl2l5l5I 59 60 61 . 68 I o I 9 I* 2 I 4 I 11 11 l1lol1IBl1!1I 69 74 75, 80 EVENT DESCRIPTION

____ _Joj 2L_jDuring an electrical storm, the 'R' Bus was de-energized causing*a complete loss I 7 8 9 80 Iola! !of off-site power, resulting in a loss of main condenser cooling water and ultimately I 7 8 9 80 lol41 I a plant trip. Primary plant was stabilized in the h~t condition and was borated. I 7 8 9 80 lalsl !Event nonrepetitive. Tech Specs 3.1.1 and 3.7.1 were violated. Electrical power I 7 8 9 80 lolsl !was restored after 4.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> and the plant returned to Tech Spec limits. (ER-77-47) I 7 8 9 Ff!IME 80 SYSTEM CAUSE COMPONENT COMPONENT COOE COOE COMPONENT CODE SUFPUER MANUFACTURER VIOLATION

@0 !El Aj ~ I ZI ZI z1*z1z1z1 ~ Iz I9 19 19 I L.:J 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION

~ I Exact cause of loss of electrical power is not known. A change to the Tech Spe_cs I 7 8 9 80 I will be made to make this type of t I event a nonviolation.

8 9 . 80 u I 7 8 9 80 FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EE] L!J 11 I 0 I 0 I ._N_/_A_ _ _ ___,I ~ IN/A 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT 7

rn 8 RELEASED

~

9 OF RELEASE

~

10 11 AMOUNT OF ACTIVITY N_/_A_ _ _ _ _

._I __.I 44 45 N/A LOCATION OF RELEASE 80 PERSONNEL EXPOSURES IIIfil I 01 01 01 NUMBER TYPE

~

OESCf11PTION

.__N_;_A_______________________________________._____--.J 7 8 9 11 12 13 80 PERS"ONNEL INJURIES

~ I 01 01 01 NUMBER DESCRIPTION

~N_/A _________________________________________________ _ J 7 8 9 11 12 80 PROBABLE CONSEQUENCES "BE NA 7 c 9 80 LOSS OR DAMAGE_ TO FACILITY DESCRIPTION N/A

.89 10 80 PUBLICITY

~ N/A 80 ADDITIONAL FACTORS

~ NA 7 8 9 60

[ili]

7 8 9 80