ML19308C330

Summary of 790904 Meeting W/N Brown & D Boltz at TMI Site Re Teaching Aids,Vendor Manuals,Sys Descriptions,Auxiliary Operator Hierarchy,Current Event Repts & Lers.Partial Deposition of ML Beers Encl

ML19308C330
Person / Time
Site:	Crane
Issue date:	10/11/1979
From:	Ornstein H, Snell J NRC - NRC THREE MILE ISLAND TASK FORCE
To:	Frampton G NRC - NRC THREE MILE ISLAND TASK FORCE
References
TASK-TF, TASK-TMR NUDOCS 8001220742
Download: ML19308C330 (22)

Text

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ca Cec UNITED STATES I.

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1. 'j, g NUCLEAR REGULATORY COMMISSION g

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October 11, 1979 MEMORANDUM FOR:

George Frampton, Deputy Director FROM:

H. L. Ornstein and J. C. Snell

SUBJECT:

RECORD OF VISIT / INFORMAL INTERVIEW WITH NELSON BROWN AND DENNIS BOLTZ - MET ED TRAINING DEPT. AT TMI SEPTEMBER 4, 1979 BY H. L. ORNSTEIN AND J. C. SNELL We started with a discussion of teaching aids, vendor manuals, and systems descriptions. Basically they indicated that in their training they use a three volume NSSS vendor manual for TMI 1; and that for TMI-2 they use a similar manual (same except for the portions on the ICS).

In addition the training department staff prepares notes for most lectures.

We discussed the hierarchy of positions that auxiliary operators go through.

We also discussed incentives for operators; i.e.,

1.

Auxiliary operators C and B are under pressure to advance to the position of auxiliary operator A; otherwise, they revert back to their position prior to auxiliary operator C (for those who were recruited from outside Met Ed, it means dismissal).

2.

Once an auxiliary operator reaches the position of Auxiliary Operator A, there is little incentive for him to become a licensed reactor operator (CRO) the pay differential is about

$27 per week, but the Auxiliary Operator does not have to undergo a requalification program, studying, etc.

3.

The Auxiliary Operators and the CR0's are members of the bargaining unit, and are " protected." Whereas the SR0's are supervisory and are not covered by the union.

The SR0's have "zero rights." The SR0 pay scale is not publicized, and salaries vary greatly among operators. Salaries are adjusted upward when the union scales for CR0's and A0's are increased, but the increases are not the same. The SR0's do not receive overtime pay as do the AO's and CR0's.

We learned the following things about Met Ed's training department:

1.

The training department people are considered " supervisory" hence they are not covered by the union bargaining unit.

8 0 01220 '/D

[

George Frampton 2

October 11, 1979 j

i 2.

The Training Department works " regular hours" - there are no

" shift rotations."

3.

There is no requirement that people in the Training Department be licensed or undergo simulator training, etc. However, if the training people who do have a license and keep it current, they receive a bonus (since they can be called in to supervise refueling, or fill in on watches).

We discussed the fact that Ed Frederick joined the Training Department subsequent to the accident. Apparently, he had applied prior to the accident.

The main reason for his wanting to switch positions was that he wanted to work " regular hours."

We discussed Current Events Reports and LERs.

Nelson (" Skip") Brown mentioned that the company does not have any written directions on covering Current Events Reports or LERs, both those generated in-house, or by the NRC. Only the in-house LERs get routed to the shifts.

It is Brown's job to review all LER's for relevance to the Training Department.

Brown stated that he did not get the 1977 Current Events Report which covered the September 1977 Davis Besse event; however, he did get NRC's and the " clearinghouse's" LER description of that event. The NRC's and the clearinghouse's description of the LER for that event did not trigger any action on his behalf since neither report discussed saturation in the core.

We discussed training with regard to saturation conditions.

It was stated that saturation conditions are discussed relative to the steam generator, in particular for the station blackout, and reactor trip from low pressure; saturation conditions in the core were never covered (since their reactor is a PWR - not a BWR).

I think that we should depose Brown so that his statements on the Current Events Report on Davis-Besse is under oath, and that we also get clarification about the " Emergency Procedures" course that he taught in 1978 (as stated in Beers' deposition before the President's Commission - see enclosure).

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H.

. Or.nstein l

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Enclosures:

1.

Beers' deposition 2.

Notes from Brown's course on Emergency Procedures

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________x PRESIDENT'S COMMISSION ON THE ACCIDENT AT THREE MILE ISLAND

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DEPOSITION of METROPOLITAN EDISON COMPANY by MARSHALL LEROY 3EERS, held at Three Mile Island Nuclear Generating Station, Harrisburg, Pennsylvania, on the 30th day of July 1979, commencing at 3:40 p.m.,

before Stanley Rudbarg, Certified Shorthand Reporter

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and Notary Public of the State of New York.

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e-BENJAMIN REPORTING SERVICE, ).

CERTIFIED SHORTHAND REPORTERS

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FivE ItCERMAN STREE7f NEW YOrlK.NEW YOltK 10038

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2 procedures, ae gensral guidelines with eight'er nina It is conceivable 3

symptoms of a particular casualty.

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that you could be in one or more emergency procedures

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Does the training program ever directly N

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address the following question, namely, you, the operator, 8

may be in a situation sometime where you fo.nf.j; g 9

emergency procedure that fits the exact symptoms that an 10 you are seeing in the plant, and therefore, you have to

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11 know how to respond, and here is how to respond.

I am 12 talking about, obviously, before the accident?

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well, l a s t y e a r, '7 8 - 7 9, we taught a class called and Skip taught 14

" emergency procedure review technique,"

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15 that class, and that was kind of what you are talking i

16 about; you were reviewing a procedure and, thinking about I

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17 what could happen outside of the procedure, and Skip

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18 can talk to you'more about how he' approached that j

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class, to talk specifically and, say, give you this 20 aut there is no procedure N

21 particular casualty and say that

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22 for that casualty, no, we have never done that.

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If you were asked the following question, in terms of 24 would your own personal answer be, what n5 your understanding of the training program?

The BENJAMIN REPORTING SERVICE

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EMERGEtiCY PROCEDURE REVIEtt TECHtlIQUE 1.

Ask the following general questions a.) UHAT?

b.

WHY?

c.

IIHEll?

d.

IIHERE?

WHAT are my indications (SYMPTOMS, AUTO ACTI0tlS)? and WHAT are my actions?

UHY are my actions required? (PURPOSE)

WHEtl must these actions be done (PROMPTLY-SOMETIME LATER)

HHERE do I look for the indications and UHERE do I go to manipulate the controls.

IIHAT - This is answered by the procedure q

SYi1PTOMS - flormally unique first j

liAtlUAL ACTIONS - IMMEDIATE llHY - This is answered by Tech Spec Basis, Limits & Precautiens and operator 3

knowledge of systems and their response UHEll - Depending on the im ortance (WHY) will determine if Immediate action (Less than 1 flinute or Follow-up (Greater than 1 Minute) is required.

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llHERE - Indication and Control Location I

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• e EMERGENCY PROCEDURE REVIEW SCHEDULE May 8,1978 - June 11,1978 UNIT I and II ON SHIFT - NOME Classroom - Procedure Review Technique Reactor Trip (1202-4) (2202-1.1)

Turbine Trip (1202-3) (2203-2.2)

June 12,1978 - July 16,.1978 UNIT I and II ON SHIFT - NOME Classroom - Procedure Review plus Test Fire 1202-31) (2202-3.1)

Flood 1202-32) (2202-3.2)

Earthquake 1202-30) (2202-3.3)

Toxic Release 1004 Section 13)

July 17,1978 - August 20, 1978 NNIT I and II ON SHIFT - NOME Classroom - NONE Augu'st 21, 1978 - September 24, 1978 UNIT I and II ON SHIFT - Review Procedures Classroom - Test Operator at the Controls (1028)

Control of Caution Tags (1037)

Hand Calculations of Tilt and Imbalance (1203-7) (2103-1.11)

CRD Equipment Failures - Malfunction Action (1202-8) (2203-1.2; 2203-1.3)

Loss of OTSG Feed (1202-26A/B)(2202-2.2)

Unanticipated Criticality (1203-10) (2202-1.2)

Loss of Baron (2203-1.1)

September 25, 1978 - October 29; 1978 UNIT I and II ON SHIFT - Review Procedures Classroom - Test loss of Reactor Coolant Makeup (1203-15) (2203-1.5)

Reactor Coolant Pump and Motor Emergencies (1203-16) (2203-1.4)

OTSG Tube Rupture (1202-5)

(2202-2.6)

Loss of Reactor Coolant / Reactor Coolant Pressure (1202-6) (2202-1 ^8)

Loss of Reactor Coolant Flow / Reactor Coolant Pump irip (1202-14) (2202-1.4) l i

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October 30, 1978 - December 3,1978 UflIT I Ofl SHIFT - ?!0flE Classroom - fl0flE UllIT II Oft SHIFT - Review Procedures

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Classroom - Test Shutdown from Outside Control Room (2202-1.10)

Station Blackout (2202-2.1)

Station Blackout without Diesels (2202-2.5)

Loss of Instrument and Service Air (2202-2.3)

Load Refection (2203-2.1)

Steam Supp'.y System Rupture (2203-2.3) i l

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REACTOR TRIP Indi dt Ap e DEPT D

Table of Effective Pages Page Date Revision Page Date Revision

gge, Date ReOision 3

26.0 51.0 c11.0 11/15/77 3

27.0 52.0 42.0 11/15/77 3

28.0 53.0 3.0 11/15/77 4.0 29.0 54.0 y

5.0 30.0 55.0 6.0 31.0 56.0' 7.0 32.0 57.0 8.0

'33.0 58.0 34.0 59.0 9.0 10.0 35.0 60.0

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24.0-49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recommands Approva!

Unit 2 Staff Recommends Approval Approval

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Date Approval M

Date Cognizant Dept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Recommends Approval f

Date 0.0 $ blt4bs Date N-/4~79 Chairman of PORC V/ Ct;ailr/ tan'of PORC Unit 1 Superintendent Approval Unit 2 Superintendant Approva!

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Date M?!

Date //

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Managar Generation Coality Assurance Approval M

Date o'))o

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THREE !4ILE ISLAtlD flUCLEAR STATI0t!

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REACTOR TRIP 1.0 SYMPTOMS umtz AI.. m PauuTHeus 1.1 Reactor trip may be due to any of the following:

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fluclear power ' 105.5% of rated power.

b.

!!uclear power 3.1.05 times reactor coolant flow (%) minus powerimbalancereduction.(31.o8)

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c.

Fluclear Power > 50.9% of rated power during operation with g/S ne R.c. Pump operating per loop. (&H $

d.

i.oss of two Reactor Coolant Pumps in one reactor coolant gg

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Reactor coolant pressure > 2355 psig. (er 40s.)

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Reactor coolant pressure < 1800 psig.

DN8R [?l0 gw/p- (6/F) g.-

Reactor coolant pressure < 10.97 T

- 4650 (f/gs y _gjo3) out h.

Reactor coolant outlet temperature > 619 F.

i.

Reactor building pressure > 4 psig.

j.

143nual reactor trip actuation.

.2 Individual and group "In Limit" lights actuate.

7g,, gjg,f.,y g,f 7;f/f//LA*W 1.3 Rapid decrease in neutron level as indicated by the iluclear Instrumentation, y/R$ v/#in#dl.4 Main turbine master, trip alarm energized.

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t1. 5-Rapid decrease in Unit load.

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2.1 Automatic Action

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All rods insert (except Group 8) gg g

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Turbine trip, stop valves close 2,###

c.

Generator breakers open O"

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Turbine by-pass valves open p P -

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Source range nuclear instrumentation high voltage energizes py

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at 5 X 10-10 amps on til-3 or til-4.. aM' /d g

b 2.2 Manual Action S# g #g g a.

Manually TRIP the reactor gg,// f c 3

b.

Verify all "in-limit" lights are actuated (except group afasre 270'Cf poQpyl 9919 Ax 78tP gy c.

Verify that turbine has tripped and generator b ers gg,qlspc Y

3 @,4 E -

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are open - if turbine has I;0T tripped - manually TRIP the '

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4r..s DRAT turbine, start lift pumps ?2 turning gear oil pump.

rt op d.

CLOSE 1ctdown isolation valve MU-V376.

( (Y) Lt -V-3').

co#568

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• ges 2;pJn1 ge/# ##,jlJ e.

START second make-up pump. Open MU-V-168 as necessary

&n M RCSS9, e lh3l<<4.u0 to maintain 100" in PZR.

(sWip7~S0477s.97D Ews r)

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Verify turbine bypass centrol valves are maintaining SM.sys-Qgfe Mz s W header pressure at 1010 psig.

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If any feedwater stations are in ha'nd, run stations back h Y,

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,.o maintain OTSG at 30,,. %uT70N: Low omm'Ath PRsssue.e mAy

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Verify PZR Htrs are off 0 80" in PZRx.Hausdorczo.rsOJ

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(.2i=/Jo7~~ 17/St/ O/ S.)

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If PZR level, gets to 20" open DH-V5B and start 3rd make-up d'

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gd/II#g f' pump and open MU-V16C/D to increase PZR level.

Y(Jf#.< l0 FOLLOW-UP ACTIOIi-----.- 911Hed**?2% ?2 /2. '4AbD.Mhkfq/*

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3.1 Ar.nounce-on page system - Reactor Trip S-A M 7#'rs,sp /,[a.n'N

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n,.ta 3.2 Initiate emergency boration using Boric Acid Mi,x Tank Pumps d ##I'*-

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(CA-P4A/B) and MU-V10 if reactor power is not below 10% in

%^#eso-N<f ) ' l minu te.

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%ti+<it.:W 3.3 Monitor make-up tank level and maintain level greater than 55" by using Maste Transfer Pumps (WOL-PSA/B) and feeding from an'

).SS l y/wr=~Ocifeer#fAM."crA4

,wift [Ed j RCBT with baron concentration greater or equal to RCS concen-g tr_ation.

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/M 3.4 Verify that the pressurizer heaters and spray have returned I

I RCS pressure to normal operating pressure of 2155 psig.N 3.5 Reduce pressurizer level setpoint to 100" (25%).

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3.6 Verify normal electrical lineup, i.e., no substation or in-plant distributica breakers are open (except generator breakers).

3.7 Check that all RMS channels are normal and that no unplanned p" "- -

0 or uncontrolled radioactive release is in progress.4--- b f r W' "-

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3.8 Compute shutdown margin calculations per 2103-1.g (Reactivity yq 3'-1.6 If shutdown marg (n is less than 1%,

Balance Calculations).

i boron should be added to the RCS.

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@ If reactor start-up is not inter.:!ed within four hours raise

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f skh<l OTSG level to 97-99% on the operating range using N feedwater g valve bypass and tube' sheet drains for level control.

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THREE MILE ISLAND NUCLEAR STATION

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TURBIrlE TRIP Table of Effective Pages CONTRO: LED COPY f::ca Date Revision Pace Date Revision Pace Date Revision 1.0 02/06/76 5

26.0 51.0 2.0 09/.13/77 6

~27.0 52.0 3.0 09/13/77 6

28.0 53.0

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4.0 09/13/77 6

29.0 54.0 3.0 30.0 55.0 6.0 31.0 56.0 7.0 32.0 57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11.0 36.0 61.0 12.0 37.0 62.0 13.0 38.0 63.0 14.0 39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0 42.0 67.0 13.0 43.0 68.0 19.0 44.0 69.0 20.0 45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recorr enfsApproval Unit 2 Staff Recom. nds oval Date Approval Approval Date CognifantD;It. head Cognizadt dew./!szh Unit 1 PORC Recommends Approval Unit 2 PORC Reckmmend Ap cval h

Date 9-MW k

Date g6 Chairrnan of PORC Chairmadof o0RC j

I PORC comments of included PORC comments of hncluded 4

(date)

'(da a)

By Date By

}

l Date L

Approva3

1. O f0!n. $,J Oate 9- / '2

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Approval

//

Date

/

Approval -~ -

Date Mgr. Operational Quality As::urance Unit Superintendent

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'THREE MILE ISLAND fiUCLEAR STATI0t!

GdkzusamewawMunc#wm-::ws TURBINE TRIP LJN i i. ll.

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3.1 SYMPTOMS 5

RUNS

.Lp 1.

ICS in the tracking mode.

BIR$~

d ager eu/ esrof 2.

Turbine stop and combined intermediate valves closed.

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• 3.

Generator breakers open and megawatts electric to zero.

PM 3

rno W) qexacmz$ower decreasing.

Neutron ppucAW

5.

Any one of the following turbine trips:

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a.

Generator trip RAS

,45#

b.

Reactor trip c.

Both feed pumps tripped d.

Moisture separator level high (/czefa//3 SSC c'uogwN e.

Vacuum <23" HG

( <.jg JQ ' //f*]

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Vibration >12 mills ( >r04,//s G /o. rec) f Y f fd g.

Loss of both turbine speed signals

(. JZo93 sesso si@u4Ls) f@

h.

Over speed RPM >1035

( 1998 ' Piw)

R 1.

Backup over speed RPM >112'

1. //

j.

Hydraulic press <1100 PSI 4/p k.

Thrust bearing failure or bearing oil <15 PSI (77/ddsT'/3/2p lh*. {

/>W So Estq 1.

EHC loss of d.c. power Shaf t oil pump <105 PSI at >l300 RPM Qu de4#'#f *4 4 s'-?

m.

n.

Loss of Stator Cooling and load not <25% after 3 5 min.

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2 of 3 exhaust hoods >225 F.

4'd p.

Manual actuation of tain turbine and generator bearing deluge syster.

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6.

Pressurizer level increasing above 220", steam pressure fro increasing from 885 psig T avg. increasing above S79 F.

(S82 Y)

J.M$')pflA M',5M 3.2 IMMEDIATE ACTION

'G r, A.

Automatic Action Turbine s(top and combined intermediate va d='al_

1.

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and generator breakers open.

Turbine bypass valves or atmospheric rel)ief open to 2.

((885) m ade-tw =sw*--

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control 895 PSI steam generator pressure on a turbine trip or 1010 PSI steam generator pressure on a.

turbine trip caused by a reactor trip.

NOTE:

The Atmospheric Relief Valves will open if k

steam generator pressure reaches 1027 PSI.

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1 3.

Pressurizer Power Operated Relief Valve open.

Moisture separator drain tank pumps trip. du,M-48 4.

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5.

ICS trips to track and run back at 20%/nin. or if J

the turbine trip is from loss of feedwater pumps, the run back is 50%/ min. to 15% power.

.6.

If both the main feed pumps have tripped, the steam drivenemergencyfeedpumpwillstart.(q# g p i s iaas,.,.s 4 2#e7F/2 04W4d 7.

The feed demand will control 0.T.S.G. at minimum L level (30").

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8.

The Turbine Motor Su:: tion Oil Pump, Bearing Oil Lift Jzdamj c,2 ////-/2..g /

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Pumps and Turning Gear Oil Pump will start as turbine TWi?7 A" 9/s'qsMiSMO speed decays.

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2.0 D RAi ) U 4:.t/SS c';.t,j,

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P.Eh h% Manad AA.~

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1.

Verify that the Turbine Stop Valves are closed, 4'

generator breakers and field breakers are open.

'0' C221ff STuree-q f

s es2 ofx ff,jtNVPart' Start the A.C. Motor S'uction Pump, the Turning Gea.-

b Il h 6 6 49R c//. PM"A Oil Pump, the Bearing Lift Pumps, and close turbine

&dAR V: 5

.l. ipr t% +vs'S extraction steam valves as follows:

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{1).M tFf CLOS M (4StageEXVlA/Bi#))

i g gxs..cxuzs-1/8 ;.:!M/,G) 6 Stage EXV4A/B b / d i 3 sr4(6

~ g7;n,grycx/sygpyr FAWS g

(dxv79 Ald

{fxyin/8.)

i 8 Stage EXV5A/B/C 10 Stage EXV6A/B/C/D EMN p s7;966.(sXud4/8)

BW'$

2.

If any feedwater stations are on hand, total fegd-

~ -N water should be reduced manually to tnat corres-

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. pending to 15% neutren power.

3.

If Diamond Power or P.eactor Master is on HAttD, run rods in manually to 15". neutron power.

3.3 FOLLOW-UP ACTION

[N) 1.

Monitor pressurizer level, R.C. pre'ssure, R.C. tempera-g7 ture, 0.T.S.G. level, and steam header presst.re.

t,.

2.

Utilize pressurizer heaters and spray control P..C. pres-I f

S,a p

sure 02155 PSIG and steam header pressure setpoint 0885

( 552)

I 3/

PSIG to control T avg. 0579 F.

Adfust makeup and. letdown 7

tzo")

j flows to control pressurizer level 0220". Adjust feed e

flow to control 0.T.S.G. levels 030".

3.

If vacuum is lost in main condenser, verify atmospheric i

(BBd i

reliefs are controlling steam generator pressure at 895

(

mr

• wrz swero<a,es-1 PSI or 1010 PIS if turbine trip was due to a reactor trip and reduce power to zero.

(Hot Standby) Add required makeup to makeup tank as Tavg. is reduced to 532"F.

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If turbine trip is due to loss of'both feed pumps, verify u>

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emergency feed pump started and is deliv'ering water to (fM-IM/6) d' g) O) qY I

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the 0.T.S.G.'s thru EF-V-30A/B with the 0.T.S.G. levels dtl l-p '&l S*

0 at 30".

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5.

Verify that the feed heater water levels are below the du IT'?

r high level alarm point and open all extraction steam g

3 valves that were closed in step 1 of manual action.

6.

Check 6th Stage Heater Drain Tank Level.

fload 43' N "'

Stop Heater Drain Pumps if level is low.

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