Text

Forwards Response to Specified Items of NUREG-0737 Re Shift Technical Advisor Training Program & ECCS Outage Rept of North Anna 1 & 2
	ML18139A953
Person / Time
Site:	Surry, North Anna
Issue date:	12/31/1980
From:	Sylvia B; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Eisenhut D; Office of Nuclear Reactor Regulation
References
	TASK-1.A.1.1, TASK-1.C.1, TASK-2.K.3.03, TASK-2.K.3.17, TASK-3.D.3.4, TASK-TM NUDOCS 8101060308
	Download: ML18139A953 (37)
	v • d • e

.l e e VIRGINIA ELECTRIC AN:0 POWER COMPANY R'ICHMOND,VJ:BGJ:NJ:A 23261 December 31, 1980 Mr. Harold R. Denton, Director Serial No. 1022 Office of Nuclear Reactor Regulation NO/DWL:ms Attn: Mr. Darrell G. Eisenhut, Director Docket Nos. 50-280 Division of Licensing 50-281 U. S. Nuclear Regulatory Commission 50-338 Washington, D. C. 20555 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7

Dear Mr. Denton:

ADDITIONAL NUREG-0737 POST-TMI REQUIREMENTS INFORMATION This letter provides to you our submittal of responses to Items I .A.1.1 and II.K.3.17 of NUREG-0737. Enclosure 1 provides information regarding the long-term STA program required by Item I.A.1.1. Phaseout of the STA program is not addressed by Enclosure 1 since there is no current plan for the eventual phase~

out of the STA program. Information on such a plan would be submitted for Staff review and approval prior to implementation.

Enclosure 2 provides the North Anna Power .Station ECCS outage information required by Item II .K. 3. 17. As stated in our response to NUREG-0737 dated Deceml:ie.r 15, 1980 (Serial No. 985), only information for North Anna Units 1 and 2 is being provided at this time. ECCS outage information for Surry Power Station will be provided on or before March 1, 1981.

Information and responses to other NUREG-0737 items have been submitted since our previously referenced December 15, 1980 submittal. A summary of these submittals and their corresponding NUREG-0737 requirements is presented below:

Item I.C.1 - Short-Term Accident and Procedures Review As indicated in our December 15, 1980 response to NUREG-0737, the Westinghouse Owner's Group has submitted a detailed description of a program to comply with Item I. C. 1. This information was provided in a letter to Mr. S. H. Hanauer (NRC) from Mr. R. W. Jurgensen (AEP, representing the Westinghouse Owner's Group) dated December 15, 1980 (Serial No. OG-47).

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VIRGINIA .ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton 2 Item II.K.3.3 - Reporting of SV/RV Failures and Challenges Vepco has submitted two Technical Specification Change Requests to the NRC for approval. These requests (Serial No. 1011 for Surry Un;its 1 and 2 and Serial No. 1012 for North Anna Unit 1, both dated December 23, 1980) address the necessary reporting requirement changes in the Surry and North Anna Technical Specifications.

Item III.D.3.4 - Control Room Habitability Vepco has submitted information regarding the control room habitability review for the North Anna Power Station dated December 30, 1980 (Serial No. 1013).

As stated in our December 15, 1980 response to NUREG-0737, the Surry Power Station information required for this item will be submitted in two parts.

The first part will be provided on or before January 19, 1981.

The information provided in this letter and the referenced submittals will be summarized and provided as an update to the report entitled Response To NUREG-0737 Post TMI Requirements. This report, which was originally provided on December 15, 1980, will be updated approximately every three months to reflect the change in status of NUREG-0737 responses.

Very truly yours,

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_ B. R. Sylvia Manager - Nuclear Operations and Maintenance Attachments

e e ENCLOSURE 1 l SHIFT TECHNICAL ADVISOR TRAINING PROGRAM

e e SHIFT TECHNICAL ADVISOR TRAINING PROGRAM The attached program compares favorably with the program proposed by INPO with regard to subject matter content of the education section, transient analysis and simulation; however, INPO's program is longer. STA's will be included in the VEPCO Licensed Operator Requalification Program to ensure that the STA's are provided with an understanding of operational concepts and philosophies in order that acceptance of the STA by operations personnel is enhanced. A comparison of time (contact hours) for various sections of the program follows:

COLLEGE LEVEL FUNDAMENTAL EDUCATION VEPCO INPO Math 72 90 Reactor Theory 48 100 Reactor Chemistry 16 30 Materials 16 40 Thermal Sciences 40 120 Health Physics 16 40 APPLIED FUNDAMENTALS Reactor Technology 32 120 Instrumentation & Control 32 Management Skills 24 40 Systems 240 200 Transient Analysis 40 30 Simulator Training 80 100 Retraining 96 80

'I ' -1 e e SHIFT TECHNICAL ADVISOR ADMINISTRATIVE REQUIREMENTS A. Education Personnel selected to become Shift Technical Advisors should have as a minimum a bachelor degree in an engineering or scientific discipline. Other degree disciplines will be evaluated on a case-by-case basis.

B. Experience Prospective Shift Technical Advisors shall have a minimum of six month's experience at the station at which they will assume the duties of Shift Technical Advisor.

C. Qualification Shift Technical Advisors will be considered qualified to perform the duties of an STA after successful completion of the Shift Technical Advisor Training Program. Successful completion shall be based upon a cumulative average of 70%, or greater, on the written examinations plus "satisfactory" on the final oral/simulator evaluation.

D. Waiver Participation of prospective Shift Technical Advisors in selected areas of the Shift Technical Advisor Training Program may be waived. The waiver will be on a case-by-case basis with the requirement that the individual attain a score of 70%, or greater, on an equivalency examination in the subject area for which the exemption is being sought. The equivalency examination shall be prepared and administered by the station Training Center Staff. In addition, the Manager-Nuclear Operations and Maintenance shall authorize the waiver based on the results of the equivalency examination and the recommendation of the Station Manager.

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I. Academic A. Mathematics (9 days)

1. Algebra

a. Basic concepts

b. Algebraic operations

c. Linear equations

d.

Exponents and radicals

e. Roots

2. Logarithms

a. Definition

b. Rules of logarithms

c. Base 10 and natural logarithms

d. Exponential and logarithmic equations

3. Geometry and Trigonometry

a. Plane geometry

b. Solid geometry

c. Trigonometric functions

d. Vectors and vector operations

4. Specialized Mathematics

a. Ratios and proportions

b. Graphing techniques

c. Systems of equations

5. Differential Calculus

a. Limits and continuity

b. Derivatives

c. Applications of derivatives

6. Integral Calculus

a. Antiderivatives

b. Definite integrals

c. Applications of integrals

7. Differential Equations

a. First order

( b.

c.

Applications of first order Linear equations

d. Applications of linear equations

-- e

8. Partial Differential Equations

( EXAMINATION - 1 DAY B. Reactor Theory (6 days)

1. Basic Nuclear Physics

a. Atomic structure

b. Nuclear terminology

c. Properties and structure of the nucleus

d. Mass defect and binding energy

2. Nuclear Fission

a. Microscopic and macroscopic cross sections

b. Fission process

c. Reaction rates and power production

d. Fission products

3. Neutron Kinetics

a. Neutron sources

b. Reactions and cross sections

c. Neutron flux

d. Neutron moderation

e. Neutron multiplication (including subcritical)

( f. Diffusion theory

g. Criticality theory 4.. Reactivity Coefficients and Poisons

a. Fuel temperature coefficient

b. Moderator temperature coefficient

c. Void coefficient

d. Pressure coefficient

e. Redistribution coefficient

f. x~on

g. Samarium

h. Boron

i. Other poisons (control rods, structural materials, etc.)

EXAMINATION - 1 DAY C. Chemistry (2 days)

1. Purpose

2. Terminology

3. Sources of Makeup Water

( a.

b.

Flash Evaporator Polishing Demineralizer

c. Condensate Storage Tanks

e

4. Secondary Chemistry

( a. Type of chemistry control

b. Condensor leakage effects

c. Steam Generator chemistry problems

d. Steam Generator corrosion

e. Secondary chemistry specifications

5. Primary Chemistry

a. Chemical addition

b. Demineralization

c. Primary chemistry specifications

d. Nuclear reactions D. Materials (2 days)

1. Introduction

a. Characteristics of an "Ideal metal"

b. Failure modes of metals

c. Metalic structure

d. Radiation effects on metals

2. Fuel Element Design

( 3. Reactor Vessel Design

4. Steam Generator Design EXAMINATION - 1 DAY E. Thermal Sciences (5 days)

1. Thermodynamics

a. Laws of Thermodynamics

b. Properties of steam and water

2. Fluid Dynamics

a. Fluid statics

b. Bernoulli's Equation

c. Static and dynamic pressures

d. Laminar and turbulent flow

e. Two phase flow

3. Heat Transfer

a. Fundamentals (conduction, convection, radiation)

b. Pool boiling c.

( d.

e.

Forced convection boiling Departure from Nucleate Boiling (DNB)

Heat exchangers

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4. Reactor Thermal Cycle

( EXAMINATION - 1 DAY F. Health Physics (2 days)

1. Radiation

a. Sources of radiation

b. Types of radiation

c. Effects of radiation on matter

2. Biological Effects

a. Micro (atomic) effects

b. Macro (cell) effects

c. Acute radiation effects

d. Chronic radiation effects

3. Radiation Protection

a. Time, distance, and shielding

b. Anti-contamination clothing

c. Respiratory protection II. Applied Fundamentals

(

A. Reactor Technology (4 days)

1. Flux Distribution and Control

a. Axial flux distribution

b. Radial flux distribution

c. ~~ and axial offset

d. Hot channel factors

e. Control rods

f. Boron

2. Reactor Core

a. Core materials

b. Thermal performance

c. Core description

d. Core capability

3. Core Physics Data

a. Startup physics data

b. Core flux mapping

c. Core thermocouple mapping

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4. Reactivity Procedures

( a. Estimated Critical Position (ECP)

b. Shutdown Margin Calculation (OP-lF)

EXAMINATION - I DAY B. Instrumentation and Control (4 days)

1. Basic Instrumentation

a. Flow measuring devices

b. Pressure measuring devices

c. Temperature measuring devices

d. Level/volume measuring devices

e. Miscellaneous measuring devices

2. Control Theory

a. Flow control circuits

b. Pressure control circuits

c. Temperature control circuits

d. Level/volume control circuits

e. Miscellaneous control circuits EXAMINATION - 1 DAY

(

III. Management Skills A. Communication (1 day)

B. Problem Solving (1 day)

C. Decisional Analysis (1 day)

IV. Systems Training (30 days)

A. Reactor Coolant System B. Residual Heat Removal System C. Chemical and Volume Control System D. Nuclear Instrumentation System

1. Excore

2. Incore

(

*** e E. Tave /Rod Control

( 1.

'* llT/Tave

2. T Control ave

3. Rod Control

4. Rod Position Indication F. Reactor Protection and Control

1. Reactor Protection - General

2. Process Protection Instrumentation

3. Overpower/Overtemperature /lT Protection

4. Pressurizer Pressure Control and Protection

5. Pressurizer Level Control and Protection

6. Steam Dump Control

7. Steam Generator Level Control and Protection G. Secondary Systems

(

1. Main Steam System

2. Steam Generators

3. Main Feedwater System

4. Main Condensate System

5. Main Turbine

6. Turbine Control and Protection

7. Steam Generator Blowdown System

8. Steam Dumps

9. Circulating Water System

10. Service Water System EXAMINATION - 1 DAY

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H. Engineered Safeguards

( 1. Safety Injection System

2. Containment

3. Containment Vacuum System

4. Containment Spray System

s. Recirculation Spray System

6. Consequence Limiting Safeguards

7. Auxiliary Feedwater System J. Electrical Distribution

1. Normal Distribution

a. 4160 vac

b. 480 vac

c. Screenwell distribution

d. Lighting

2. Emergency Distribution

(. a. 4160 vac

b. 480 vac

c. Vital Busses

d. DC distribution K. Primary Support Systems

1. Component Cooling Water System

2. Chilled Component Cooling Water System

3. Charging Pump Cooling Water System

4. Primary Grade Water System

5. Liquid Waste System

6. Gaseous Waste System

7. Ventilation System

8. Core Cooling Monitor

9. PORV and Safety Valve System

( 10. Auxiliary Shutdown Panel

11. Status Lights

12. Loose Parts Monitoring System (North Anna only)

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L. Radiation Monitoring

( 1. General Detector Curve

2. Radiation Monitoring System EXAMINATION - I DAY V. Accident/Transient Analysis (5 days)

A. Transient Analysis Methodology B. Core Reload Design C. Physics Related Safety Analysis Input D. Core Thermal Hydraulic Analysis E. System Transient Analysis F. Non-LOCA Transient Analysis

1. Rod withdrawal from subcritical

2. Rod withdrawal at power

(_ 3. Dropped rod

4. Feedwater System malfunction

5. Excessive load increase

6. eves malfunction

7. Startup of inactive reactor coolant loop

8. Loss of flow

9. Single rod withdrawal

10. Loss of normal feedwater

11. Loss of offsite power

13. Feedline break

14. Steam Generator tube rupture

15. Inadvertant Safety Injection

16. Steamline break

( 17. Rod ejection

18. Locked rotor (fuel performance)

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G. Loss of Coolant Accident

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1. Large

2. Small H. Best Estimate Transient Analysis

1. North Anna cooldown event

2. Surry pump coastdown

3. Simulator loss of load comparison VI. Simulator Training (10 days)

A. Malfunctions

1. Single

a. Steam Generator tube rupture

b. Loss of rod control

c. Loss of feedwater

d. Reactor/turbine/generator trip

e. Small break LOCA I{ f. Large break LOCA

g. Loss of RCS pressure

h. Steam Generator level malfunction

i. Uncontrolled cooldown of RCS

j. Loss of flow

k. Loss of electrical bus (4160 vac)

1. Loss of RHR

2. Multiple Malfunctions

--to be determined based on the class's performance

3. Normal Operations

a. Reactor startup

b. Reactor shutdown

c. Power maneuvers VII. COMPREHENSIVE EXAMINATION A. Written - l day B. Oral/Simulator - 1/2 day

(

i ENCLOSURE 2 ECCS OUTAGE REPORT NORTH ANNA POWER STATION UNITS 1 AND 2

ECCS OUTAGE REPORT This report is concerned with the outages of the Emergency Core Cooling System (ECCS) of North Anna Units land 2, conmenci_ng with the issuing of the fuel loading license of each unit. The data collected is presented as a response to the requirements of NUREG 0737, Item II.k.3.17-1 and will address the following four criteria as required by NUREG 0737.

These four criteria are: (1) outage dates and duration of outages; (2) cause of the outage; (3) ECCS systems or components involved in the outage; (4) corrective action taken.

The primary methods utilized in collecting the data consisted of identifying the ECCS systems/components to be examined, and of reviewing all action statement logs for the appropriate time period in order to answer question no. 1, no. 3 and to an extent question no. 2. In order to answer question no. 4, and to an extent question no. 2, completed maintenance reports and periodic surveillance tests were retrieved from Station Records and reviewed. Other documents used in the review included control room operator logs, shift supervisor logs, equipment tagging reports and completed outstanding maintenance lists.

The equipment identified as ECCS equipment and the total outage duration times are as follows for each unit.

HOURS Emergency Diesel Generator and Associated Unit l 468 (lH Diesel)

Subsystems 166.5 (lJ Diesel)

Unit 2 184.25 (2H Diesel) 92.5 (2J Diesel)

High Head Safety Injection System Unit 1 172 Unit 2 4.5 Low Head Safety Injection System Unit 1 44.5 Unit 2 88 Refueling Water Storage Tank Unit 1 24.5 Unit 2 l Inside and Outside Recirculation Spray Unit 1 21.5 Unit 2 59.5 Casing Cooling Systems Unit 1 445.5 Unit 2 7

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HOURS Safety Injection Accumulators Unit l 24.5 Unit 2 32 Boron Injection System Unit l 68.5 Unit 2 272.5 Service Water System Unit l l 00. 75 Unit 2 29.5

Page 1 of 3 NORTH ANNA POWER STATION UNIT ill l ECCS OUTAGE REPORT ELECTRICAL POWER SYSTEM OUTAGE OUTAGE COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION 1-H Emergency Preventative Maintenance Completed Maintenance 09-01-78 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Diesel Generator Repair and re-install diesel Fastened racks to concrete 12-02-78 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months

_____________b_a_t_t_e_rY

__r_a_c_k_s_______________w_a_1_1____________________________

03-02-79 Preventative Maintenance Completed Maintenance to 77 .5 hrs 03-05-79 Remove angle iron on lip of Ground out pieces of angle 05-03-79 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months exhaust ducting outlet iron Semi-Annual Preventative Completed Maintenance 08-02-79 7 .5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Maintenance 02-02-80 Diesel tripped on high crank- Pressure switch recali-to 47 hours5.439815e-4 days 0.0131 hours 7.771164e-5 weeks 1.78835e-5 months case Pressure brated - SAT.

02-04-80 02-15-80 Diesel tripped on Overspeed Reset speed control governor to 46 hours5.324074e-4 days 0.0128 hours 7.60582e-5 weeks 1.7503e-5 months 02-17-80 03-02-80 Diesel tripped on Overspeed Replaced hi speed relay to 38 hours4.398148e-4 days 0.0106 hours 6.283069e-5 weeks 1.4459e-5 months -

03-04-80 Diesel tripped on Lube Oil Crank- Inspected diesel, performed 03-06-80 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months case Low Pressure periodic test Fitting leaks at pressure switch Tightened fitting and recali-(EG-PS-603H) inside skid mounted brated pressure switch. Ran 03-16-80 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Control Panel diesel - no leaks Gasket on oil filter inside tightened packing and plug 03-21-80 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months radiator house - leaking on drain valve 04-03-80 Tripped on overspeed on Replaced Governor to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months emer. start (SI) 04-04-80

Page 2 of 3 NORTH ANNA POWER STATION UNIT ifal ECCS OUTAGE REPORT ELECTRICAL POWER SYSTEM (continued)

OUTAGE OUTAGE COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION 04-30-80 1-H Emergency Preventative Maintenance Complete Maintenance to 49.5 hrs Diesel Generator 05-02-80 Tripped on overspeed - emer.

start (SI)

Preventative Maintenance Replace with a new modified woodward governor Complete Maintenance 05-23-80 to 05-26-80 09-22-80 10-02-80 83.5 hrs 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Preventative Maintenance Complete Maintenance to 51 hours5.902778e-4 days 0.0142 hours 8.43254e-5 weeks 1.94055e-5 months 10-04-80 Remove lH from service to install Install agastat and tested 11-16-80 5.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months agastat in diesel output breaker 1-J Emergency Semi-Annual Preventative Complete Maintenance 11-16-78 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Diesel Generator Maintenance Repair and re-install diesel Fastened battery racks to 12-02-78 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months battery racks concrete wall Semi-Annual Preventative Complete Maintenance 02-16-79 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Maintenance Preventative Maintenance Complete Maintenance 03-16-79 5.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Remove angle iron on lip of Ground out pieces of angle 05-04-79 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months exhaust ducting outlet iron 09-26-79 Governor reset-cooldown 21.5 hrs Tripped on overspeed to for refuel 09-27-79

Page 3 of 3 NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT ELECTRICAL POWER SYSTEM (continued)

OUTAGE OUTAGE COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION 1-J Emergency Accuracy check on crankcase Calibrated and installed Diesel Generator 03-12-80 49 .5 hrs pressure switch new switch Auxiliary oil pump out of service Preventative Maintenance Replaced overload assembly auxiliary contact Complete Maintenance 03-24-80 05-22-80 to 05-23-80 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months 27 hours Preventative Maintenance Complete Maintenance 09-22-80 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 10-16-80 Preventative Maintenance Complete Maintenance to 47.5 hrs 10-18-80 Remove J diesel from service to Install agastat, perform install agastats in diesel out- 11-16-80 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months periodic test put breaker

Page 1 of 1 NORTH ANNA POWER STATION UNIT #1 .

ECCS OUTAGE REPORT HIGH HEAD SAFETY INJECTION SYSTEM OUTAGE OUTAGE-COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION Complete test 10 hour*s A-Charging Pump Periodic Surveillance Test 01-27-79 Two pumps still available Crack ground out and re-Vent valve on suction line cracked welded. Two pumps remain available 05-13-79 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months e

Seal replaced and pump B-Charging Pump Outboard Seal Leakage tested. Two pumps remain 07-14-78 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months available Complete Testing Periodic Testing 03-20-80 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months Two pumps remain available 09-30-80 Complete Maintenance Preventative Maintenance to 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months Two pumps still available 10-01-80 C-Charging Pump Blown oil seal on inboard bearing Inboard pump seal leakage Replace oil seal Two pumps remain available Repair inboard mechanical seal 04-03-78 07-17-78 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months 13 hours Oil filter retainer ring Oil leak on oil strainer replaced. Two pumps remain 03-19-80 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months available

Placement of charging pump lB in operable status was delayed in order to shim the outboard seal to reduce charging pump lB outboard seal leakage. During this time, 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 11 minutes, only one pump was operable.

Page 1 of 1 NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT LOW HEAD SAFETY INJECTION SYSTEM OUTAGE OUTAGE-COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION B-Low Head Pump Preventative Maintenance Complete Maintenance 10-16-78 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Preventative Maintenance Complete Maintenance 11-28-78 1.5 hrs e

A-Low Head Pump Preventative Maintenance Complete Maintenance 11-03-78 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Preventative Maintenance Complete Maintenance 11-28-78 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months MOV 1863A Discharge 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Perform Periodic Surveillance Test Complete Testing 05-11-79 to Charging Pumps Check Valves in SI discharge lines Discharge Valve 1890D Inservice Inspection - Periodic Testing No light indication Complete testing Fuse holder tightened 05-03-80 05-19-80 1.5 hrs 22.5 hrs Valve would not electrically Replaced locking ring on 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months MOV 1885D B-Pump 06-23-80 operate. light module

Page 1 of 1 NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT QUENCH SPRAY SYSTEM COMPONENT OUTAGE OUTAGE CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION Refueling Water Level below specifications due Made up to tank 04-29-78 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Storage Tank to a Safety Injection Temperature >50°F due to a Chillers placed in service -

Safety Injection 04-29-78 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months -

Temp. lowered Boron concentration low due to Borate and make up to tank 04-29-78 2.5 hrs a Safety Injection Engineering determined that an Lowered level to new excessive column of water is being 09-12-79 1.5 hrs specification maintained in the tank

'.Cool Level low due to a safety injection Refill Tank ;',09-25-79 down for refueling 04-03-80 Level low due to a safety injection Refill Tank to 4.5 hrs 04-04-80

Page 1 of 3 NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT RECIRCULATION SPRAY SYSTEM OUTAGE OUTAGE COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION 09-22-78 Casing Cooling Tank Temperature> 50°F Placed on chiller to 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months 09-23-78 Freon leak from the tank chiller System recharged with freon.

temperature to 08-19-79 5.5 hrs Vendor to locate freon leak.

08-12-78 Casing Cooling LlP high as found on Periodic Vented pressure gage -

to 120 hrs Pump 3A surviellance test test redone 08-17-78 Changed oil, completed Preventative Maintenance 05-25-79 .5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months inspection Bearing housing disassembled Leakage from outboard pump seal cleaned and inspected. Casing 6-6-79 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months surface reground to set 0-ring Preventative Maintenance Complete Maintenance 06-12-80 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Preventative Maintenance

~p high as found on Periodic surviellance test Complete Maintenance Vented pressure gage -

test redone 07-03-80 08-11-80 to 08-13-80 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 57 hours Casing Cooling .5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Preventative Maintenance Complete Maintenance 05-25-79 Pump 3B 08-27-79 Testing indicated pump ~p too high Vented pressure gage to 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months 08-29-79

Page 2 of 3 NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT RECIRCULATION SPRAY SYSTEM (continued)

COMPONENT OUTAGE OUTAGE CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION Casing Cooling 09-14-79 Unknown Unknown to 139 hrs Pump 3B 09-20-79 Casing Cooling Tank Preventative Maintenance Complete Maintenance Built temporary enclosure 07-26-80 3.5 hrs Level controller frozen 12-29-79 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months level xmitter ground gage Place heat tracing around Design change 01-30-80 2 .5 hrs transmitter 02-29-80 Replace with a seismic Level xmitter not approved to 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months approved xmitter 03-01-80 Outside Recirc.

Spray Pump A Special testing Preventative Maintenance Completed testing Completed Maintenance 01-10-80 11-28-80

.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hrs 11-07-80 Outside Recirc.

Periodic Testing Completion of testing to 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months Spray Pump B 11-08-80 Preventative Maintenance Complete Maintenance 11-28-80 1.5 hrs

Page 3 of 3 NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT RECIRCULATION SPRAY SYSTEM (continued)

OUTAGE OUTAGE COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION Inside Recirc.

Preventative Maintenance Complete Maintenance 11-28-78 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Spray Pump A Inside Recirc.

Spray Pump B Design change 79-S64 Fuse and fuse blocks changed out on design change 10-06-80 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Page 1 of 2 NORTH ANNA POWER STATION UNIT 1/1 ECCS OUTAGE REPORT SAFETY INJECTION SYSTEM OUTAGE OUTAGE COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION Accumulator C Level> 7756 gal (T.S. limit) Lowered level 10-02-78 1 hou~

Pressure low when accum. discharged Returned level and pressure to relief tank thru RHR relief after 03-06-79 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to limit.

RHR outlet valves opened.

Boron concentration too high due 01-26-80 Feed and bleed accumulator to stratification within the to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months until within specifications accumulators 01-27-80 Boron concentration too high due Feed and bleed accumulator to stratification within the 11-24-80 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months until within specifications accumulators Boron concentration too high due Feed and bleed accumulator 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Accumulators B, C to stratification within the 01-26-80 until within specifications accumulators Accumulator B Boron concentration too high due to stratification within the accumulators Feed and bleed accumulator until within specifications 08-01-80 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months e Boron concentration too high due Feed and bleed accumulator to stratification within the 09-04-80 2.5 hrs until within specifications accumulators Boron Injection 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Level low due to a Safety Injection Make up to BIT 04-30-78 Tank (BIT)

.',Cooled Low level due to a Safety Injection Make up to BIT ,',Q9 79 down for refuelin

Page 2 of 2 NORTH ANNA POWER STATION UNIT /11 ECCS OUTAGE REPORT SAFETY INJECTION SYSTEM (continued)

COMPONENT OUTAGE OUTAGE CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION Boron Injection 02-23-80 Boron concentration and temp low Return to specification to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Tank (BIT) 02-24-80 Boron concentration level, temp low - Safety Inj.

Return to specifications 04-03-80 to 04-04-80 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months e Boron concentration low Return to specifications 05-30-80 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months BIT - Check Valve Check valve failed to hold 1-SI-66 Unknown 08-22-78 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months pressure for testing BIT SI-304 Valve plugged with Boric Acid Cleaned out line 02-13-80 9.5 hrs

Page 1 of 2 NORTH ANNA POWER STATION UNIT ill ECCS OUTAGE REPORT SERVICE WATER SYSTEM COMPONENT OUTAGE OUTAGE CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION Service Water 09-18-78 Preventative Maintenance -

Pump lA Complete Maintenance to 5 hou-rs Change oil 09-19-78 Preventative Maintenance -

Complete Maintenance 11-29-78 1. 5 hrs Polarization Index Ratio Periodic Test III - Pump Tilt Complete Measurements 05-16-79 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Measurements Periodic Test III - Pump Tilt Complete Measurements 01-10-80 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Measurements Preventative Maintenance Complete Maintenance 03-07-80 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Service Water Unknown Unknown 07-06-78 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Pump 1B Hi discharge pressure as per Periodic test 75.2B Retested using more accurate flow device 07-26-78 to 07-28-78 33.5 hrs e Periodic Test III - Pump Tilt Complete Measurements 03-15-79 2 .5 hrs Measurements Periodic Test III - Pump Tilt Complete Measurements 01-10-80 2.5 hrs Measurements Periodic Test III - Pump Tilt Complete Measurements 11-24-80 .25 hrs Measurements

Page 2 of 2 NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT SERVICE WATER SYSTEM (continued)

COMPONENT OUTAGE OUTAGE CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION No water found, no maint-MOV 108A, B Water in Limitorque 08-18-78 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months enance done Flow xmitter 10-29-80 Transmitter replaced and Service Water Transmitter out of tolerance to 37 .5 hrs calibrated 10-30-80

Page 1 of 2 NORTH ANNA POWER STATION UNIT #2 l,

ECCS OUTAGE REPORT ELECTRICAL POWER SYSTEM OUTAGE OUTAGE.

COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION Emergency Diesel Preventative Maintenance Complete Maintenance 05-28-80 7 hOU:!S Gen. 2H 05-28-80 Preventative Maintenance Complete Maintenance to 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months 05-29-80 08-05-80 Preventative Maintenance Complete Maintenance to 34 hours3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months 08-06-80 10-01-80 Preventative Maintenance Complete Maintenance to 4.5 hrs 10-02-80 XF-1 Jacket Heater Transformer Replaced transformer XF-1 10-15-80 4.5 hrs burned out 2H Diesel Fuel Level switch, on fuel oil Fuel oil pump did not start 10-15-80 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months Oil Pump tank, operation tested Emergency Diesel Gen. 2J Diesel tripped after 20 seconds Performed periodic test 82.lB 05-17-80 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Preventative Maintenance Complete Maintenance 05-28-80 15.5 hrs Auxiliary lube oil xformer Replaced xformer and 6.5 hrs 06-06-80 burned out tested - sat.

10-16-80 Preventative Maintenance Complete Maintenance to 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months 10-18-80

Page 2 of 2 NORTH ANNA POWER STATION UNIT #2 ECCS OUTAGE REPORT ELECTRICAL POWER SYSTEM (continued)

COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION OUTAGE OUTAGE

*- DATES DURATION Emergency Diesel Diesel batteries failed Periodic Recalculated test by Gen. 2J 12-01-80 6.25 hrs test normalizing data

Page 1 of 1 NORTH ANNA POWER STATION UNIT #2 I..

ECCS OUTAGE REPORT HIGH HEAD SAFETY INJECTION SYSTEM OUTAGE OUTAGE COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION Charging Pump lC Shutdown pump - repair seal Outboard pump seal leaking 10-08-80 4.5 hr; Two pumps remain available Safety Injection Pump lA Fitting on seal supply leaks Repair fitting (tighten and test) 06-10-80 07-01-80 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months -

Lamp test design change mod. Complete modification to 41 hours4.74537e-4 days 0.0114 hours 6.779101e-5 weeks 1.56005e-5 months 07-03-80 07-01-80 Safety Injection Lamp test design change mod. Complete modification to 41 hours4.74537e-4 days 0.0114 hours 6.779101e-5 weeks 1.56005e-5 months Pump 1B 07-03-80 Relief valve on discharge line Pulled valve, adjusted lift- 12.5 hrs 09-19-80 lifting at too low a pressure setting and placed back in system MOV 2890 A, C LHSI Discharge Valves Packing Leaks Tighten Packing 07-28-80 .5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months MOV 2862 A MOV 2885A Packing Leaks Tighten Packing 07-28-80 .5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months MOV 2864A MOV 2890B MOV 2862B Packing Leaks Tighten Packing 10-30-80 .5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months MOV 2885B

Page 1 of 1

/" .

NORTH ANNA POWER STATION UNIT #2 ECCS OUTAGE REPORT RECIRCULATION SPRAY SYSTEM OUTAGE OUTAGE COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATION Casing Cooling Preventative Maintenance Complete Maintenance 06-13-80 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Pump 3A Casing Cooling Pump 3B Preventative Maintenance Complete Maintenance 06-21-80 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 06-29-80 Recirc. Spray Lamp Test Modification Modification Complete to 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Pump 2A 06-30-80 06-24-80 Recirc. Spray Lamp Test Modification Modification Complete to 15 .5 hrs Pump 2B 06-25-80 06-30-80 Inside Recirc.

Lamp Test Modification Modification Complete to 32.5 hrs Spray Pump IA 07-01-80 Inside Recirc. Mechanical Linkage on breaker 24Jl-2 Breaker removed, cleaned and 11-25-80 2.5 hrs Spray Pump 1B for pump - did not operate replaced. Tested satisfactorily

Page 1 of 1 NORTH ANNA POWER STATION i -.

UNIT #2 .....

ECCS OUTAGE REPORT QUENCH SPRAY SYSTEM COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION OUTAGE OUTAGE DATES DURATI.ON Refueling Water .,.

Feed and bleed tank until 09-09-80 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Storage Tank Boron concentration> 2105 PPM within limits

- --- -- - - _______ ____j

NORTH ANNA POWER STATION UNIT f/:2 Page 1 of 1 ECCS OUTAGE REPORT SAFETY INJECTION SYSTEM COMPONENT OUTAGE OUTAGE.

CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATIGN 08-07-80 In Mod~

Accumulator A, B, C Feed and bleed until within Boron concentration >2100 PPM to 5 - Acc.

specs.

08-13-80 not needed Accumulator A Boron concentration >2100 PPM Feed and bleed until within specs.

09-11-80 to 09-12-80 27.5 hrs Accumulator C Feed and bleed until within Boron concentration> 2100 PPM 10-09-80 1.5 hrs specs.

Feed and bleed until within Boron concentration> 2100 PPM 10-09-80 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months specs.

Boron Injection Tank (BIT)

Boron concentration low Boron concentration low Batch to Boric Acid Storage tank Batch to Boric Acid Storage tank 05-20-80 to 05-21-80 05-21-80 to 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months 120 hrs 05-26-80 05-27-80 Batch to Boric Acid Storage Boron concentration low to 124 hrs tank 06-02-80 Batch to Boric Acid Storage 10-08-80 .5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months tank Batch to Boric Acid Storage 10-20-80 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months tank

?: ..

Page 1 of 1

NORTH ANNA POWER STATION ~ -

UNIT #2 '\.- .

ECCS OUTAGE REPORT SERVICE WATER SYSTEM OUTAGE OUTAGE.,,

COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION DATES DURATIOij Service Water Lamp Test Modification Complete Modification 06-29-80 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Pump lA Service Water Pump 1B Lamp Test Modification Complete Modification 06-23-80 to 06-24-80 21.5 hrs -

--

ML18139A953

Text

Dear Mr. Denton:

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