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)
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e VIRGINIA ELECTRIC AN:0 POWER COMPANY R'ICHMOND,VJ:BGJ:NJ:A 23261 December 31, 1980 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

ADDITIONAL NUREG-0737 POST-TMI REQUIREMENTS INFORMATION Serial No. 1022 NO/DWL:ms Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 This letter provides to you our submittal of responses to Items I.A.1.1 and II.K.3.17 of NUREG-0737. 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. 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,

, c<J () O) ~-'-

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"' [ ~'it4M B. R. Sylvia Manager - Nuclear Operations and Maintenance Attachments

e SHIFT TECHNICAL ADVISOR TRAINING PROGRAM e

l ENCLOSURE 1

e SHIFT TECHNICAL ADVISOR TRAINING PROGRAM e

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

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A.

Education SHIFT TECHNICAL ADVISOR ADMINISTRATIVE REQUIREMENTS e

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.

b.

c.

d.

Plane geometry Solid geometry Trigonometric functions 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.

b.

c.

d.

First order Applications of first order Linear equations Applications of linear equations

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8.

Partial Differential Equations EXAMINATION - 1 DAY e

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.

b.

c.

d.

e.

f.

g.

Neutron sources Reactions and cross sections Neutron flux Neutron moderation Neutron multiplication (including subcritical)

Diffusion theory 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.

c.

Flash Evaporator Polishing Demineralizer Condensate Storage Tanks

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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.

b.

c.

d.

e.

Fundamentals (conduction, convection, radiation)

Pool boiling Forced convection boiling Departure from Nucleate Boiling (DNB)

Heat exchangers

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II.

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4.

- -e Reactor Thermal Cycle EXAMINATION - 1 DAY F.

Health Physics (2 days)

1.

Radiation

a.

Sources of radiation

b.

Types of radiation e

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 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

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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

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E.

F.

G.

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/Rod ave Control

1.

llT/T ave

2.

T ave Control

3.

Rod Control

4.

Rod Position Indication 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 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

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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

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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.

17.

Steamline break Rod ejection

18.

Locked rotor (fuel performance)

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G.

Loss of Coolant Accident

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

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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

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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.

Emergency Diesel Generator and Associated Subsystems High Head Safety Injection System Low Head Safety Injection System Refueling Water Storage Tank Inside and Outside Recirculation Spray Casing Cooling Systems HOURS Unit l 468 (lH Diesel) 166.5 (lJ Diesel)

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

Unit 1 172 Unit 2 4.5 Unit 1 44.5 Unit 2 88 Unit 1 24.5 Unit 2 l

Unit 1 21.5 Unit 2 59.5 Unit 1 445.5 Unit 2 7

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..,I 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

COMPONENT 1-H Emergency Diesel Generator CAUSE OF OUTAGE Preventative Maintenance NORTH ANNA POWER STATION UNIT ill ECCS OUTAGE REPORT ELECTRICAL POWER SYSTEM CORRECTIVE ACTION Completed Maintenance Repair and re-install diesel Fastened racks to concrete Page 1 of 3 OUTAGE DATES 09-01-78 l

OUTAGE DURATION 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 ___________________________ _

Preventative Maintenance Remove angle iron on lip of exhaust ducting outlet Semi-Annual Preventative Maintenance Diesel tripped on high crank-case Pressure Diesel tripped on Overspeed Diesel tripped on Overspeed Diesel tripped on Lube Oil Crank-case Low Pressure Fitting leaks at pressure switch (EG-PS-603H) inside skid mounted Control Panel Gasket on oil filter inside radiator house - leaking Tripped on overspeed on emer. start (SI)

Completed Maintenance Ground out pieces of angle iron Completed Maintenance Pressure switch recali-brated - SAT.

Reset speed control governor Replaced hi speed relay Inspected diesel, performed periodic test Tightened fitting and recali-brated pressure switch.

Ran diesel - no leaks tightened packing and plug on drain valve Replaced Governor 03-02-79 to 03-05-79 05-03-79 08-02-79 02-02-80 to 02-04-80 02-15-80 to 02-17-80 03-02-80 to 03-04-80 03-06-80 03-16-80 03-21-80 04-03-80 to 04-04-80 77.5 hrs 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 47 hours 46 hours5.324074e-4 days 0.0128 hours 7.60582e-5 weeks 1.7503e-5 months 38 hours -

14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 hours 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

COMPONENT 1-H Emergency Diesel Generator 1-J Emergency Diesel Generator CAUSE OF OUTAGE Preventative Maintenance NORTH ANNA POWER STATION UNIT ifal ECCS OUTAGE REPORT ELECTRICAL POWER SYSTEM (continued)

CORRECTIVE ACTION Complete Maintenance Tripped on overspeed - emer.

start (SI)

Replace with a new modified woodward governor Preventative Maintenance Preventative Maintenance Remove lH from service to install agastat in diesel output breaker Semi-Annual Preventative Maintenance Repair and re-install diesel battery racks Semi-Annual Preventative Maintenance Preventative Maintenance Remove angle iron on lip of exhaust ducting outlet Tripped on overspeed Complete Maintenance Complete Maintenance Install agastat and tested Complete Maintenance Fastened battery racks to concrete wall Complete Maintenance Complete Maintenance Ground out pieces of angle iron Governor reset-cooldown for refuel Page 2 of 3 OUTAGE OUTAGE DATES DURATION 04-30-80 to 49.5 hrs 05-02-80 05-23-80 to 83.5 hrs 05-26-80 09-22-80 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 10-02-80 to 51 hours5.902778e-4 days 0.0142 hours 8.43254e-5 weeks 1.94055e-5 months 10-04-80 11-16-80 5.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 11-16-78 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 12-02-78 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months -

02-16-79 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 03-16-79 5.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 05-04-79 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 09-26-79 to 21.5 hrs 09-27-79

COMPONENT 1-J Emergency Diesel Generator NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT ELECTRICAL POWER SYSTEM (continued)

CAUSE OF OUTAGE Accuracy check on crankcase pressure switch Auxiliary oil pump out of service Preventative Maintenance Preventative Maintenance Preventative Maintenance Remove J diesel from service to install agastats in diesel out-put breaker CORRECTIVE ACTION Calibrated and installed new switch Replaced overload assembly auxiliary contact Complete Maintenance Complete Maintenance Complete Maintenance Install agastat, perform periodic test Page 3 of 3 OUTAGE OUTAGE DATES DURATION 03-12-80 49.5 hrs 03-24-80 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months

05-22-80 to 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months 05-23-80 09-22-80 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 10-16-80 to 47.5 hrs 10-18-80 11-16-80 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months

COMPONENT A-Charging Pump B-Charging Pump C-Charging Pump NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT HIGH HEAD SAFETY INJECTION SYSTEM CAUSE OF OUTAGE Periodic Surveillance Test Vent valve on suction line cracked Outboard Seal Leakage Periodic Testing Preventative Maintenance Blown oil seal on inboard bearing Inboard pump seal leakage Oil leak on oil strainer CORRECTIVE ACTION Complete test Two pumps still available Crack ground out and re-welded. Two pumps remain available

Seal replaced and pump tested.

Two pumps remain available Complete Testing Two pumps remain available Complete Maintenance Two pumps still available Replace oil seal Two pumps remain available Repair inboard mechanical seal Oil filter retainer ring replaced.

Two pumps remain available Page 1 of 1 OUTAGE DATES 01-27-79 05-13-79 07-14-78 03-20-80 09-30-80 to 10-01-80 04-03-78 07-17-78 03-19-80 OUTAGE-DURATION 10 hour*s 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 72 hours 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 32 hours 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months 13 hours 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

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.

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COMPONENT B-Low Head Pump A-Low Head Pump MOV 1863A Discharge to Charging Pumps Check Valves in SI discharge lines Discharge Valve 1890D MOV 1885D B-Pump NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT LOW HEAD SAFETY INJECTION SYSTEM CAUSE OF OUTAGE CORRECTIVE ACTION Preventative Maintenance Complete Maintenance Preventative Maintenance Complete Maintenance Preventative Maintenance Complete Maintenance Preventative Maintenance Complete Maintenance Perform Periodic Surveillance Test Complete Testing Inservice Inspection - Periodic Complete testing Testing No light indication Fuse holder tightened Valve would not electrically Replaced locking ring operate.

light module Page 1 of 1 OUTAGE OUTAGE-DATES DURATION 10-16-78 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 11-28-78 1.5 hrs e 11-03-78 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 11-28-78 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 05-11-79 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 05-03-80 1.5 hrs

05-19-80 22.5 hrs on 06-23-80 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

COMPONENT Refueling Water Storage Tank NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT QUENCH SPRAY SYSTEM CAUSE OF OUTAGE Level below specifications due to a Safety Injection Temperature >50°F due to a Safety Injection Boron concentration low due to a Safety Injection Engineering determined that an excessive column of water is being maintained in the tank Level low due to a safety injection Level low due to a safety injection CORRECTIVE ACTION Made up to tank Chillers placed in service -

Temp. lowered Borate and make up to tank Lowered level to new specification Refill Tank Refill Tank Page 1 of 1 OUTAGE OUTAGE DATES DURATION 04-29-78 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 04-29-78 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months -

04-29-78 2.5 hrs 09-12-79 1.5 hrs

'.Cool

',09-25-79 down for refueling 04-03-80 to 4.5 hrs 04-04-80

COMPONENT Casing Cooling Tank Casing Cooling Pump 3A Casing Cooling Pump 3B CAUSE OF OUTAGE Temperature> 50°F NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT RECIRCULATION SPRAY SYSTEM CORRECTIVE ACTION Placed on chiller Freon leak from the tank chiller System recharged with freon.

temperature to Vendor to locate freon leak.

LlP high as found on Periodic surviellance test Preventative Maintenance Leakage from outboard pump seal Preventative Maintenance Preventative Maintenance

~p high as found on Periodic surviellance test Preventative Maintenance Testing indicated pump ~p too high Vented pressure gage -

test redone Changed oil, completed inspection Bearing housing disassembled cleaned and inspected.

Casing surface reground to set 0-ring Complete Maintenance Complete Maintenance Vented pressure gage -

test redone Complete Maintenance Vented pressure gage Page 1 of 3 OUTAGE DATES 09-22-78 to 09-23-78 08-19-79 08-12-78 to 08-17-78 05-25-79 6-6-79 06-12-80 07-03-80 08-11-80 to 08-13-80 05-25-79 08-27-79 to 08-29-79 OUTAGE DURATION 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months 5.5 hrs -

120 hrs

.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 8 hours 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 3 hours *-

57 hours6.597222e-4 days 0.0158 hours 9.424603e-5 weeks 2.16885e-5 months

.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 54 hours

COMPONENT Casing Cooling Pump 3B Casing Cooling Tank level xmitter Outside Recirc.

Spray Pump A Outside Recirc.

Spray Pump B NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT RECIRCULATION SPRAY SYSTEM (continued)

CAUSE OF OUTAGE Unknown Preventative Maintenance Level controller frozen Design change Level xmitter not approved Special testing Preventative Maintenance Periodic Testing Preventative Maintenance CORRECTIVE ACTION Unknown Complete Maintenance Built temporary enclosure ground gage Place heat tracing around transmitter Replace with a seismic approved xmitter Completed testing Completed Maintenance Completion of testing Complete Maintenance Page 2 of 3 OUTAGE DATES 09-14-79 to 09-20-79 07-26-80 12-29-79 01-30-80 02-29-80 to 03-01-80 01-10-80 11-28-80 11-07-80 to 11-08-80 11-28-80 OUTAGE DURATION 139 hrs 3.5 hrs -

5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2.5 hrs 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months

.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months -

1.5 hrs 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months 1.5 hrs

COMPONENT Inside Recirc.

Spray Pump A Inside Recirc.

Spray Pump B CAUSE OF OUTAGE NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT RECIRCULATION SPRAY SYSTEM (continued)

CORRECTIVE ACTION Preventative Maintenance Complete Maintenance Design change 79-S64 Fuse and fuse blocks changed out on design change Page 3 of 3 OUTAGE OUTAGE DATES DURATION 11-28-78 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months -

10-06-80 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

COMPONENT Accumulator C Accumulators B, C Accumulator B Boron Injection Tank (BIT)

NORTH ANNA POWER STATION UNIT 1/1 ECCS OUTAGE REPORT SAFETY INJECTION SYSTEM CAUSE OF OUTAGE Level> 7756 gal (T.S. limit)

Pressure low when accum. discharged to relief tank thru RHR relief after RHR outlet valves opened.

Boron concentration too high due to stratification within the accumulators Boron concentration too high due to stratification within the accumulators Boron concentration too high due to stratification within the accumulators Boron concentration too high due to stratification within the accumulators Boron concentration too high due to stratification within the accumulators Level low due to a Safety Injection Low level due to a Safety Injection CORRECTIVE ACTION Lowered level Returned level and pressure to limit.

Feed and bleed accumulator until within specifications Feed and bleed accumulator until within specifications Feed and bleed accumulator until within specifications Feed and bleed accumulator until within specifications Feed and bleed accumulator until within specifications Make up to BIT Make up to BIT Page 1 of 2 OUTAGE DATES 10-02-78 03-06-79 01-26-80 to 01-27-80 11-24-80 01-26-80 08-01-80 09-04-80 04-30-78

,',Q9-25-79 OUTAGE DURATION 1 hou~

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 hours -

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 12 hours 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months e 2.5 hrs 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months

.',Cooled down for refuelin

COMPONENT Boron Injection Tank (BIT)

BIT - Check Valve 1-SI-66 BIT SI-304 Boron Boron low -

Boron CAUSE OF OUTAGE concentration and NORTH ANNA POWER STATION UNIT /11 ECCS OUTAGE REPORT SAFETY INJECTION SYSTEM (continued)

CORRECTIVE ACTION temp low Return to specification concentration level, temp Return to specifications Safety Inj.

concentration low Return to specifications Check valve failed to hold pressure for testing Unknown Valve plugged with Boric Acid Cleaned out line Page 2 of 2 OUTAGE OUTAGE DATES DURATION 02-23-80 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 02-24-80 04-03-80 e

to 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 04-04-80 05-30-80 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 08-22-78 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months 02-13-80 9.5 hrs

COMPONENT Service Water Pump lA Service Water Pump 1B NORTH ANNA POWER STATION UNIT ill ECCS OUTAGE REPORT SERVICE WATER SYSTEM CAUSE OF OUTAGE Preventative Maintenance -

Change oil Preventative Maintenance -

Polarization Index Ratio Periodic Test III - Pump Tilt Measurements Periodic Test III - Pump Tilt Measurements Preventative Maintenance Unknown Hi discharge pressure as per Periodic test 75.2B Periodic Test III - Pump Tilt Measurements Periodic Test III - Pump Tilt Measurements Periodic Test III - Pump Tilt Measurements CORRECTIVE ACTION Complete Maintenance Complete Maintenance Complete Measurements Complete Measurements Complete Maintenance Unknown Retested using more accurate flow device Complete Measurements Complete Measurements Complete Measurements Page 1 of 2 OUTAGE OUTAGE DATES DURATION 09-18-78 to 5 hou-rs 09-19-78 11-29-78

1. 5 hrs -

05-16-79 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 01-10-80 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 03-07-80 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 07-06-78 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 07-26-78 to 33.5 hrs e 07-28-78 03-15-79 2.5 hrs 01-10-80 2.5 hrs 11-24-80

.25 hrs

COMPONENT MOV 108A, B Flow xmitter Service Water CAUSE OF OUTAGE Water in Limitorque NORTH ANNA POWER STATION UNIT #1 ECCS OUTAGE REPORT SERVICE WATER SYSTEM (continued)

CORRECTIVE ACTION No water found, no maint-enance done Transmitter out of tolerance Transmitter replaced and calibrated Page 2 of 2 OUTAGE DATES 08-18-78 10-29-80 to 10-30-80 OUTAGE DURATION 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 37.5 hrs

COMPONENT Emergency Diesel Gen. 2H 2H Diesel Fuel Oil Pump Emergency Diesel Gen. 2J NORTH ANNA POWER STATION UNIT #2 ECCS OUTAGE REPORT ELECTRICAL POWER SYSTEM CAUSE OF OUTAGE Preventative Maintenance Preventative Maintenance Preventative Maintenance Preventative Maintenance XF-1 Jacket Heater Transformer burned out Fuel oil pump did not start Diesel tripped after 20 seconds Preventative Maintenance Auxiliary lube oil xformer burned out Preventative Maintenance CORRECTIVE ACTION Complete Maintenance Complete Maintenance Complete Maintenance Complete Maintenance Replaced transformer XF-1 Level switch, on fuel oil tank, operation tested Performed periodic test 82.lB Complete Maintenance Replaced xformer and tested - sat.

Complete Maintenance Page 1 of 2 l,

OUTAGE OUTAGE.

DATES DURATION 05-28-80 7 hOU:!S 05-28-80 to 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months 05-29-80 08-05-80 to 34 hours3.935185e-4 days 0.00944 hours 5.621693e-5 weeks 1.2937e-5 months 08-06-80 10-01-80 to 4.5 hrs 10-02-80 10-15-80 4.5 hrs 10-15-80 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months 05-17-80 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 05-28-80 15.5 hrs 06-06-80 6.5 hrs 10-16-80 to 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months 10-18-80

COMPONENT CAUSE OF OUTAGE NORTH ANNA POWER STATION UNIT #2 ECCS OUTAGE REPORT ELECTRICAL POWER SYSTEM (continued)

CORRECTIVE ACTION Page 2 of 2 OUTAGE OUTAGE DATES DURATION Emergency Diesel Gen. 2J Diesel batteries failed Periodic test Recalculated test by normalizing data 12-01-80 6.25 hrs -

COMPONENT Charging Pump lC Safety Injection Pump lA Safety Injection Pump 1B MOV 2890 A, C LHSI Discharge Valves MOV 2862 A MOV 2885A MOV 2864A MOV 2890B MOV 2862B MOV 2885B NORTH ANNA POWER STATION UNIT #2 ECCS OUTAGE REPORT HIGH HEAD SAFETY INJECTION SYSTEM CAUSE OF OUTAGE CORRECTIVE ACTION Shutdown pump - repair seal Outboard pump seal leaking Two pumps remain available Repair fitting (tighten and test)

Fitting on seal supply leaks Lamp test design change mod.

Complete modification Lamp test design change mod.

Complete modification Relief valve on discharge line Pulled valve, adjusted lift-lifting at too low a pressure setting and placed back in system Packing Leaks Tighten Packing Packing Leaks Tighten Packing Packing Leaks Tighten Packing Page 1 of 1 I..

OUTAGE OUTAGE DATES DURATION 10-08-80 4.5 hr; 06-10-80 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 07-01-80 to 41 hours4.74537e-4 days 0.0114 hours 6.779101e-5 weeks 1.56005e-5 months 07-03-80 07-01-80 to 41 hours4.74537e-4 days 0.0114 hours 6.779101e-5 weeks 1.56005e-5 months 07-03-80 09-19-80 12.5 hrs -

07-28-80

.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 07-28-80

.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 10-30-80

.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

COMPONENT Casing Cooling Pump 3A Casing Cooling Pump 3B Recirc. Spray Pump 2A Recirc. Spray Pump 2B Inside Recirc.

Spray Pump IA Inside Recirc.

Spray Pump 1B NORTH ANNA POWER STATION UNIT #2 ECCS OUTAGE REPORT RECIRCULATION SPRAY SYSTEM CAUSE OF OUTAGE Preventative Maintenance Preventative Maintenance Lamp Test Modification Lamp Test Modification Lamp Test Modification Mechanical Linkage on breaker 24Jl-2 for pump - did not operate CORRECTIVE ACTION Complete Maintenance Complete Maintenance Modification Complete Modification Complete Modification Complete Breaker removed, cleaned and replaced.

Tested satisfactorily Page 1 of 1 OUTAGE DATES 06-13-80 06-21-80 06-29-80 to 06-30-80 06-24-80 to 06-25-80 06-30-80 to 07-01-80 11-25-80

/"..

OUTAGE DURATION 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 4 hours 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months 15.5 hrs -

32.5 hrs 2.5 hrs

COMPONENT Refueling Water Storage Tank CAUSE OF OUTAGE NORTH ANNA POWER STATION UNIT #2 ECCS OUTAGE REPORT QUENCH SPRAY SYSTEM CORRECTIVE ACTION Boron concentration> 2105 PPM Feed and bleed tank until within limits Page 1 of 1 i

OUTAGE OUTAGE DATES DURATI.ON 09-09-80 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

_______ ____j

COMPONENT Accumulator A, B, C CAUSE OF OUTAGE NORTH ANNA POWER STATION UNIT f/:2 ECCS OUTAGE REPORT SAFETY INJECTION SYSTEM CORRECTIVE ACTION Boron concentration >2100 PPM Feed and bleed until within specs.

Page 1 of 1 OUTAGE DATES 08-07-80 to 08-13-80 OUTAGE.

DURATIGN In Mod~

5 - Acc.

not needed -

Accumulator A Boron concentration >2100 PPM Accumulator C Boron concentration> 2100 PPM Boron concentration> 2100 PPM Boron Injection Boron concentration low Tank (BIT)

Boron concentration low Boron concentration low Feed and bleed until within specs.

Feed and bleed until within specs.

Batch to Boric Acid Storage tank Batch to Boric Acid Storage tank Batch to Boric Acid Storage tank Batch to Boric Acid Storage tank Batch to Boric Acid Storage tank 09-11-80 to 09-12-80 10-09-80 10-09-80 05-20-80 to 05-21-80 05-21-80 to 05-26-80 05-27-80 to 06-02-80 10-08-80 10-20-80 27.5 hrs 1.5 hrs 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 25 hours -

120 hrs 124 hrs

.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 3 hour

Page 1 of 1

?:..

NORTH ANNA POWER STATION

~ -

UNIT #2

'\\.-..

ECCS OUTAGE REPORT SERVICE WATER SYSTEM COMPONENT CAUSE OF OUTAGE CORRECTIVE ACTION OUTAGE OUTAGE.,,

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

--

ML18139A953

Text

Dear Mr. Denton:

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