ML20135F074

Corrected Discussion of Potentially Objectionable Matl Being Taught by General Physics Corp in Containment Leak Rate Course in Nov 1983.Objectionable Matl Covered Interactions W/Nrc.Listing of Course & Newsletter Encl

ML20135F074
Person / Time
Site:	Oyster Creek
Issue date:	09/04/1985
From:	Dircks W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:	NRC COMMISSION (OCM)
References
NUDOCS 8509170143
Download: ML20135F074 (1)

Text

,

g September 4, 1985 K 7 'O G N3

'E S %W MEMORANDUM FOR:

The Commissioners FROM:

William J. Dircks Executive Director for Operations

SUBJECT:

GENERALPHYSICSCORPORATIONINSTRUCTIONALCOURSCFOR LICENSEES CONTAINING MATERIAL OBJECTIONABLE TO THE NRC e

On August 22, 1985, NRC:HQ management learned of potentially objectionable material being taught by General Physics Corporation (GP), a contractor to General Public Utilities Corporation (GPU), in a containment leak rate course given in November 1983. A RIII inspector obtained the material from a co-worker who had attended the GP course when employed by GPU at their Oyster Creek facility.

NRC management reviewed the material and after discussions with 01 and ELD contacted General Physics (Enclosure 1).

The objectionable portion of the material covered interactions with the NRC. The material appears to suggest or condone practices that could be misleading to the NRC program of inspection which relies to a large extent on licensee candor. As a result of Mr. Taylor's telephone conversations on August 23 and 24,1985 with representatives of GP, the company responded with a letter dated August 26, 1985 (Enclosure 2) identifying 17 GPU/0yster Creek full time participants in the

~

offering at Oyster Creek and 8 participants from 4 utilities (names deleted by NRC) in a subsequent course held March 1 and 2, 1984. Some of the objectionable material was deleted from the subsequent course offering.

The NRC staff is continuing followup with GP regarding the extent of dissemi-nation of this or similar materials. Also, the staff will followup with the identified utilities which had individuals taking these courses.

For information, GP conducts training, provides technical reference material and engineering services under contract to utilities. A listing of GP courses and workshops and reference material extracted from a GP newsletter (Enclosure

3) is provided for infomation. General Physics presently has 5 contracts with the NRC (Enclosure 4).

(S?;::cS ESa J.D!r:ks William J. Dircks Executive Director for Operations

Enclosures:

As stated 8509170143 850904 cc: SECY PDR ADOCK 05000219 PDR OGC P

OPE

/

Distribution: /

DS A DO R/F JMTaylor BGrimes Dircks DR RHVollmer SASchwartz JPartlow QRoe DEPER R/F >

ELJordan JAxelrad i

ELD i Rehm Stello

/

EDO M

D:DEP{

E D IE D'

h WJDircks ELJor-RH mer J a 9/3/95:jr d 5

9 3/85AJ 9/3/85

oncoq jo,,

UNITED STATES NUCLEAR REGULATORY COMMISSION e

o E

,I WASHINGTON. D C. 20555

\\..../

t v

August 26, 1985 MEMORANDUM FOR:

File FROM:

James M. Taylor, Director y

Office of Inspection and Enforcement

SUBJECT:

GENERAL PHYSICS CORPORATION With reference to the attached letter to General Phystes Corporation, I was called at my home on Saturday, August 24, 1985 by Mr. Whitney, Vice President. Mr. Whitney told me the following:

1.

Thecourse,"ContainmentSystemsLeakageTesting7asdescribed in the outline of Lecture #3 had been taught only once.

That had been for the Oyster Creek Station of GPU on November 29 and 30, 1983.

2.

Based on a student's comments which were critical of a portion on interaction ~with the NRC, the course had been revised.

The revised course was taught only one more time in Columbia, Md.

Personnel from BG&E, HL&P, CP&L, Duquesne, Vepco, Texas Utilities, an'd Consumers had attended.

3.

He (Mr. Whitney) will send me a copy of the revised course with further details.

)

e. Ta r,

irector Of ice of spection and Enforcement cc:

W. Dircks V. Stello H. Denton G. Cuhningham B. Grimes J. Partlow[

E. Jordan J. Blaha Regional Administrators l

goNOd N

g Enclosure 2 gnb l

h 90 Sbe

/t d

GENERAL PHYSICS CORPORATION 10 HICKOR Y RfDGE 4 COLU MAR YLAND N044 301 964-6000-982 1240

.iAY WHITNEY I

Wee President and Chief Administrative Officer August 26, 1985 GP-L-g10742 i

Mr. James M. Taylor Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission

/

Washington, DC 20555 Dear Mr. Taylors Confirming our telephone conversations on August 23 and 24, 1985, General Physics conducted its Containment Systems Leakage Testing Course twice:

(1) on November 29 and 30, 1983, for GPU Nuclear Corporation and (2) on March 1 and 2, 1984, for several utilities. Copies of the course attendance lists are enclosed.

Following the initial conduct of the' course in November 1983, General l

Physics revised Lecture #3 concerning Interactions with the NRC. Copies of

'the original and revised viewgraphs for this lecture are enclosed. As you can see from the revised viewgraphs, all of the viewgraphs that were questioned were revised.

General Physics has not conducted this course since March 1984 and cur-rently we do not offer the course. Rather, we are offering a course on Integrated Leak Rate Testing which focuses on hardware and procedure matters and does not address directly interactions with the NRC.

In reviewing this matter, I want to point out again that the viewgraphs that were questioned are only a small part of the course. When taken in con-text, the course specifically stresses the importance of working with the NRC in fulfilling the public health and safety responsibilities associated with containment systems leakage testing.

You can be asqured of our full cooperation in resolving this matter to your satisfaction.

I Sincerely, GENERAL PHYSICS CORPORATION H,

/N

.n"dW s

JWatl Enclosures O(p d 1

ENERAL PHYSICS CORPORATION CONTAINMENT TESTING COURSE (based on 10CTR50, Appendix J)

FOR CPU NUCLEAR CORPORATION AT CYSTER CREEK NUCLEAR GENERATING STATION W

CDNPLETICM ETETUS FOR COURSE ETITNIEES FUI.L TIME PARTICIPANTS, TWO-DAY CTMr IST COURSE:

17 total (awarded 1.4 CE' based on 75% or greater attendance)

Ilames deleted o

i i

PART TIME PARTICIPANTS: less than 75% attendances CIUs not awarded No part time attendees i.

L e

h i

f f

=-_

Pcg3 1 of 2 GENERAL PHYSICS CORPORATION Columbia, Maryland CONTAIN.5ENT TESTING COURSE ATTENDEES March 1 & 2, 1984 I

p-

,e 1.

Name deleted Baltimore Gas & Electric Co=pany Calvert Cliffs Nuclear Power Plant Routes 2 & 4 Lusby, m 20657 HoustonLightingandPowerCompah 2.

! lame deleted 4

P.O. Box 510 Wadsworth, Texas 77414 3-ifame deleted Baltimore Gas & Electric Co.

Calvert Cliffs Nuclear Power Plant Route 2 & 4 Lusby, MD 20657 4-

- Ilame deleted Carolina Power & Light Company Shearon Harris Nuclear Power Plant P.O. Box 165 Niw Hill, NO 27568 5.

flame deleted Duquesne Light Company Beaver Valley Power Station - Unit 1 P.O. Box 4

~~

~

Shippingport, PA 15077 6.

flame deleted Baltimore cas & Electric Company l

Calvert Cliffs Nuclear Power Plant Route 2 & 4 Lusby, m 20657 7.

ilame deleted Daquesne Light Co=pany Beaver Valley Power Station - Unit 1 P.O. Box 4 Shippingport, PA 15077 8..-

flame deleted Virginia Electric Power Company North Anna Power Station -

P.O. Box 402 Mineral, VA 23117 l

-w a-.,

s a,

• u-w_+_

-.a a_m_.

_-.mm_

-a 4

e e

f 1

E t

l3 ll e

i r

i

~

LECTURE #3 j

j INTERACTIONS WITH THE NRC I

,! b t

i l I i

l l

1 i

l l Il 1.

)

J 4

i i,

e

.i

]

~ !

.=

i m

J i.

3-0

KEY PHASES s

e e

CONSTRUCTION PERMIT - PSAR COMMITMENTS 2

e OPERATING LICENSE - FSAR COMMITMENTS & TECH SPECS

~

.)

e PREOPERATIONAL TEST - LOTS OF ATTENTION s

COMMERCIAL OPERATIONS-UPDATES AND PERIODIC TESTS 9

OPERATING LICENSE RENEWALS -UPDATES AND PLANT MODIFICATIONS j

SUBMITTALS AND UPDATES i

e SARs (PSAR, FSAR)- CONTAINMENT AND SYSTEMS e

TEC,HNICAL SPECIFICATIONS - SUBMIT AT LEAST 6 MONTHS PRIOR TO USE

[

(10CFR50.55a(g)(S)(ii))

e EXEMPTIONS TO 10CFR50 APPENDIX J a.

0 RELIEF REOJESTS FOR ASME SECTION XI VALVE TESTING l

e PREOF AND PERIODIC ILRT

SUMMARY

REPORTS (INCLUDES LLRT TESTING

SUMMARY

SINCE LAST ILRT) j e

S.ECONDARY CONTAINMENT TESTING REPORT (PER TECH SPECS) e LIAISON EVENT REPORTS (REPORTABLE OCCURRENCES)

J j-e ASME SECTION XI REPAIR / REPLACEMENTS, AS APPLICABLE (NIS-2 FORM l

AVAILABLE PER W82A & LATER) 3-1 i

s -

INTERACTIONS WITH THE NRC INSPECTION AND ENFORCEMENT AUDITS

.D 4

PROGRAM COMMITMENTS (FSAR & TECH SPECS) 7 9

RECORD 5 OF REQUIRED TESTS / INSPECTIONS S

PROCEJJRES 8

REPAIR AND REPLACEMENT ACTIONS 9

INSTRUMENTATION /CAllBRATION PROGRAM g

ANTICIPATING NRC ACTION / RESPONSES 9

LOCAL / REGIONAL (SURVEILLANCE AND ENFORCEMENT)

~

PERSONAL INTERESTS AND KNOWLEDGE AFFECT AREAS SCRUTINIZED AND EMPHASIS II Li INSPECTOR'S PREJJDICE WILL VARY ON INTERPRETATION / APPLICATION OF REQUIREMENTS l

NRC POSITION CAN BE " GUESSED" BASED ON EXPERIENCE e

EXPERIENCE AT OTHER PLANTS PREVIOUS INSPECTIONS 7

_)

REGIONAL PREFERENCES MUST BE CONSIDERED e

CENTRAL OFFICE - PREPARES / REVISES REGULATIONS, REG. GUIDES; ISSUES 3-2

4-I d

[

]

DAY TO DAY COMMUNICATIONS (INDUSTRY EXPERIENCES) 1 l

9 SHOULD THE UTILITY INFORM THE NRC OF CONTEMPLATED PROGRAM '

CHANCES? THIS IS DEBATABLE.

l ALERTING NRC OPENS UP UTILITY FOR COMMENTS AND SECOND THOU GHTS.

SPRINGING CHANGES ON NRC HAS BENEFIT OF SURPRISE. '

NOTE: IT SEEMS BETTER TO KEEP NRC INFORMED ON KEY ISSUES AND i

TO COMMUNICATE WITH THE INSPECTOR. LOG AND DOCUMENT

- COMMUNICATIONS.

l

' BENEFITS: UTILITY CAN LEARN OF NRC POSITION APRIORI. IF NO REVIEW IS PERFORMED, UTILITY CAN DEFEND ACTIONS BY SAYING "THE NRC HAD SUFFICIENT TIME TO COMMENT (BJT DID NOT)... THIS, WAS ASSUMED TO CONSITUTE TACIT APPROVAL."

a b.

{

1 3-3

l I

i 4*

4 i

e INTERACTIONS WITH THE NRC P

t

+

L3 DAY TO-DAY COMMUNICATIONS (CONTD) i e

INFORMING THE LOCAL INSPECTOR t

i IT'S IMPORTANT TO KEEP LOCAL INSPECTOR INFORMED OF CURRdNT DEVELOPMENTS ENCOURAGE INSPECTOR TO WITNESS A TYPE C TEST, BUT... DON'T c

h BE FOOLISH:

NOTE: PERFORM DEMO ON AN " EASY" VALVE WHICH HAS sj TRADITIONAL,LY NOT BEEN A " PROBLEM LEAKER" 4

NRC WILL WANT TO CONCENTRATE ON PAST PROBLEM AREAS AND PET L

PEEVES PLANT STAFF SHOULD REVIEW ALL NRC COMMENTS / PROBLEMS WITH l

PAST JLRTs AND ENSURE PROPER RESOLUTION EXAMPLE: VALVE LINEUP (BEFORE AND AFTER TESTING; CHECK

'~

PLANT HISTORY) e e

9 3

a I

e 1

3-4

INTERACTIONS WITH THE NRC t

P DAY 10 - DAY COMMUNICATIONS (CONTD)

/,

~

e TRADITIONAL INDUSTRY APPROACH TO ILRT TESTING PROBLEMS HAS BEEN i

PREDICATED ON NOT STATING TO NRC:

j WHEN THE TEST BECAN (THJS ALLOWING FOR REPAIRS AFTER PRESSURIZATION COMMENCED)

A

.h THE " TYPE A" TEST FAILED (SINCE SOME SMOOTH TALKERS HAVE MANAGED TO GET OUT OF FAILURES)

WE'LL DO IT OVER (SINCE IT HAS BEEN POSSIBLE TO OBTAIN NRC j,

AGREEMENT WITH SUCH STATEMENTS AS, "YOU SAW THE TEST BEFORE

{

AND DIDN'T COMMENT; WHY THIS TIME WHEN WE'VE DONE IT EVEN

-BETTER?")

~~

NOTE:

' DISCUSSION OF THE ABOVE EXPERIENCE SHOULD IN NO WAY INDICATE' I

ENDORSEMENT OF ANY OF THESE OBSERVED APPROACHES.

l m

I c--

i r-l t

)

['

l" 1

~

l l

4 I

1 I

3-S l

INTERACTIONS WITH THE NRC t

.3 KEY CONSIDERATIONS IN PEPARING PROGRAM

-~

w e

REVIEW PLANT DESIGN FOR INSPECTABILITY/ TESTABILITY j

9 DETERMINE AREAS OF NONCOMPLIANCE WITH REGULATIONS, CODES, STANDARDS, ETC.

9 PREPARE EXEMPTION REQUESTS FOR APPENDIX J PROGRAM (TYPE A, B & c p

TESTS)

F G

PREPARE RELIEF REQUESTS FOR ASME SECTION XI, CATEGORY A VALVE i

TESTING e

DISCUSS MAJOR PROGRAM CONCEPTS / CHANGES WITH NRC EARLY IN DEVELOPMENT e., PERFORM DEVELOPMENTAL AND IMPLEMENTATION TASKS AS EARLY AS

~

POSSIBLE s

REDUCE EXCEPTIONS TO TESTING - COMPLETE PLANT MODIFICATIONS

-o 0

J l

-.__--v,v----

y-w

---

,r

l INTERACTIONS WITH THE NRC SOME NRC POSITIONS

[

.a

! 7 9

ANSI 56.8 - 1981 VS. ANSI N45.4 -1972

-}

ANSI 56.8 IS NOT REQUIRED BY NRC FOR PLANTS BJ1LT TO ANSI N45.4

,1 DEPENDING ON YOUR REGION, NRC STAFF MAY REQUIRE L

COMPLIANCE WITH PORTIONS OF ANSI 56.8 NOTE: NRC PLANS TO ACCEPT ANSI 56.8 BY REG. GUIDE

~

9 BECHTEL TOPICAL REPORT BN-TOP-l NRC DOES NOT LIKE SHORT DURATION TESTING BJT...

-NRC HAS (AND IS EXPECTED TO) ACCEPT THE SHORTENED ILRT ON A CASE BASIS

({

9 ILRT - lLRT, SEQUENCE CONSIDERATION 1

NRC RECOGNIZES THAT ILRT FAILURE "HAS TEETH" 7

PUBLIC WILL BE PROTECTED IF INTEGRATED LEAKAGE IS "IN SPEC" CONSIDERING ILRT BEFORE LLRT TO DETERMINE "AS FOUND" CONTAINMENT LEAKAGE CONDITION i

REVISION TO 10CFR50 APPENDIX J CONTINJES i

3-7

f a!!!

si :s i

s' si II al if s

E Sj $8l i'

I!

Ei I

_l

! is !!

i:i :i !

1i i' 8

!j 3

!;a-al !5 f

a e

5 g

e gI 5.asEj g*5si a fi o

1 fi g

' l

[ni s

r IE

=

a; i:

a; i!ja, 111 1 if I it s' T

i ri i

run i i i t_.2 T. T gi 59 g((i

!)

-5 j

ji aj vf a.i t

I a!

vi-a*g aj

[s!

a;,g

[

.s g 'f 5

as ai!

1 1

i3 l8 Egr 6

L:-

E g ;-

r

=i si av

[!

a 5:a gv gi s

r r

v i

g 3

Il f

i gj[a:g 35 i

i I

I g

"s s

Ir r

o ar a

al u

h 8

5 g

=-

5!

5!

SI a!!

n!!s 5

r ey el is, E-ag, 5-5 1

I isg :t e

!5 g*'

!! =.

1-o Es

!=

=

=

e E'

l f

5 f

3 #

a 1

i s

I I

I i

i 3

g r-8-

u

-1

.o aI z

vi s!

a 8

o

?

g ag af aI aE 5

r V:-

5:

95 Ir l'

E=i

-rs el

• Ed g:if lEg 3

il er Ei a:

rg I-11 Ii E:

a!,

r E'

i ag 1

33 I

I I

I I

• b I

EG 3E!

b I

=

a'!

Eg 33 af a:2 all li lE!

8

~:

11 ali I

r si s ' 'l g

s 3

n 33 5

!3 I

I I

l 8

'~

g f

t

l i

t J

.12 1

1 LECTURE #3 j

INTERACTIONS WITH THE NRC WI g

• 4 t

t i

P '"

l

',f-4 u

, l' l,'

l 6l a

em I

mye l1 9

l'm

.4 M

3-0 "I"

KEY PHASES t

3 4

CONSTRUCTION PERMIT - PSAR COMMITMENTS e

OPERAT!NG LICENSE - FSAR COMMITMENTS & TECH SPECS 9

PREOPERATIONAL TEST - LOTS OF ATTENTION

/

G COMMERCIAL OPERATIONS - UPDATES AND PERIODIC TESTS e

OPERATING LIGNSE RENEWALS - UPDATES AND PLANT MODIFlCATIONS SUBMITTALS AND UPDATES e

SARs (PSAR, FSAR)- CONTAINMENT AND SYSTEMS 4

TECHNICAL SPECIFICATIONS - SUBMIT AT LEAST 6 MONTHS PRIOR TO USE l

(10CFRSO.55a(gX5Xii))

l 9

EXEMPTIONS TO 10CFRSO APPENDIX J e

RELIEF REQUESTS FOR ASME SECTION Xl VALVE TESTING

~

e PREOP AND PERIODIC ILRT

SUMMARY

REPORTS (INCLUDES LLRT TESTING

SUMMARY

S1NCE LAST ILRT)

[

G SECONDARY CONTAINMENT TESTING REPORT (PER TECH SPECS) u F:

O LICENSEE EVENT REPORTS (REPORTABLE OCCURRENCES)

, tJ e

ASME SECTION XI REPAIR / REPLACEMENTS, AS APPLICABLE (NIS-2 FORM AVAILABLE PER W82A & LATER)

REVISED i

3-1 I

d LNSPECTION AND ENFORCEMENT AUDITS f

J e

PROGRAM COMMITMENTS (FSAR & TECH SPECS)

)

a e

RECORDS OF REQUIRED TESTS / INSPECTIONS

.)

4 PROGOURES 4

REPAIR AND REPLAGMENT ACTIONS

~

4 INSTRUMENTATION / CALIBRATION PROGRAM L.:

r-L, ANTICIPATING NRC ACTION / RESPONSES e

LOCAL / REGIONAL (SURVEILLANG AND ENFORCEMENT) j L

PERSONAL INTERESTS AND KNOWLEDG AFFECT AREAS SCRUTINIZED AND EMPHASIZED r-lLe INSPECTOR'S PREJUDICE WILL VARY ON I

INTERPRETATION / APPLICATION OF REQUIREMENTS NRC POSITION CAN BE " GUESSED" BASED ON EXPERIENCE l

o EXPERIENG AT OTHER PLANTS

~

o PREVIOUS INSPECTIONS l

n U

REGIONAL PREFERENGS MUST BE CONSIDERED e

CENTRAL OFFICE - PREPARES / REVISES REGULATIONS, REG. GUIDES; ISSUES POSITIONS 3-2 REVISED

1 I

l l

t Y

3 DAY TO DAY _COMMUNICATlONS (INDUSTRY EXPERIENGS)

J 4

TFE UTILITY SHOULD INFC3M THE NRC OF CONTEMPLATED PROGRAM 2

~

CHANTS KEEP NRC INFORMED ON KEY ISSUES AND TO COMMUNICATE WITH 4

THE INSPECTOR. LOG AND DOCUMENT COMMUNICATIONS.

\\

BEtEFITS: UTILITY CA,N LEARN OF NRC POSITION APRIORI. (F NO REVIEW IS PERFORMED, UTILITY CAN DEFEND ACTIONS BY SAYING "THE NRC HAD SUFFICIENT TIME TO COMMENT (BUT DID NOT)... THIS WAS ASSUMED TO CONSITUTE TACIT APPROVAL."

i e

s 8

)

l e

l t

l l

REVISr.D 3-3

t 3

DAY-TO-DAY CO' MUNICATiONS (CONTD)

M j

e INFORMING TM LOCAL INSPECTOR

)

IT'S IMPORTANT TO KEEP LOCAL INSPECTOR INFORMED OF CURRENJ DEVELOPNENTS j

ENCOURAGE INSPECTOR TO WITNESS A TYPE C TEST, BUT PERFORM DEMO ON AN ' EASY" VALVE WHICH HAS TRADITIONALLY NOT BCEN A b

" PROBLEM LEAKER" i

4 NRC WILL WANT TO CONCENTRATE ON PAST PROBLEM AREAS AND PET t 3 PEEVES e

PLANT STAFF SHOULD REVIEW ALL NRC COMMENTS / PROBLEMS WITH i

PAST ILRTs AND ENSURE PROPER RESOLUTION j

EXAMPLE: VALVE LINEUP (BEFORE AND AFTER TESTING; CHECK PLANT HISTORY)

~

9 I

.J

'.b

• *D 3-4 l

~

t i

+

3

~.

KEY CONSIDERATIONS IN PEPARING PROGRAM

-)

e REVIEW PLANT DESIGN FOR INSPECTABILITY/ TESTABILITY i

G DETERMINE AREAS OF NONCOMPLIANG WITH REGULATIONS, CODES, STANDARDS, ETC.

l-0 PREPARE EXEMPTION REQUESTS FOR APPENDIX J PROGRAM (TYPE A, B & C l :.

TESTS) l-'L.

PREPARE RELIEF R50 VESTS FOR ASME SECTION XI, CATEGORY A, VALVE e

TESTING e

DISCUSS MAJOR PROGRAM CONCEPTS /CHAN25 WITH NRC EARLY IN DEVELOPMENT e

PERFORM DEVELOPMENTAL AND IMPLEMENTATION TASKS AS EARLY AS POSSIBLE i

e REDUCE EXCEPTIONS TO TESTING-COMPLETE PLANT MODIFICATIONS j

l j

1.4:

l REVISED 3-5 l

i.

SOME NRC POSITIONS

[

3 v

9 ANSI 56.8 - 1981 VS. ANSI N45.4 -1972 f/

w ANSI S6.815 NOT REQUIRED BY NRC FOR PLANTS BUILT TO ANSI N45.4 1

DEPENDING ON YOUR REGION, NRC STAFF MAY REQUIRE COMPLIANCE WITH PORTIONS OF ANS156.8 i

NOTE: NRC PLANS TO ACCEPT ANSI 56.8 BY REC. GUIDE l

( :

e DECHTEL TOPICAL REPORT'BN-TOP-l

'k.

NRC DOES NOT LIKE SHORT DURATlON TESTING BUT...

l i

NRC HAS (AND 15 EXPECTED TO) ACCEPT THE SHORTENED ILRT ON A s._

_ CASE BASIS 4

LLRT - lLRT SEQUENCE CONSIDERATION 1.

NRC RECOGNIZES THAT ILRT FAILURE ' MAS TEETH" 6.

l PUBLIC WILL BE PROTECTED IF INTEGRATED LEAKAGE IS "lN SPEC" NRC l'S CONSIDERING ILRT BEFORE LLRT TO DETERMlNE "AS FOUND" CONTAINMENT LEAKAGE CONDITION REVISION TO 10CFRSO APPENDIX J CONTINUES LJ e

I REVISED 3-6

,.. ~ _ _ _.... _ _. _, _,, _,

S' 7

.g

.I!!

!! Er r

..j It i; i a

)

t.k r

n r;

.v.l rg

=

4 3,

l, si j3

• 3 s

}; s*

- v r

8C I

g {y 2

a 55 {[ j !! [3 wl B' gI 3

i

~

yy ';I 1

r g g~i a:

a 1:

3 IIl;*

5 a..I B

15 t

EX 5:

B; 'i a

r

]

5 5?gi i I!

! I! :

1 Ij

~!

g3ng a

rrr iii r u r.T 3-3

• 5

P

!=

5I

• s

?

li

-g I

i.

t

.V 2;

!!.*')

a!

ai 8

5 r

a=! l;$

a!

35!

l I

I T[

si

g lj!

[g 5

g e!

g Ils v

.g I-i m

=

E.

g-g[n I

l b

h f

I ag!

i i

i i

i v!

g 3

_ II F-E Is "T

o ar a

i t:.

'g j

u n

8 5

{

t E

g l'is!

sl si si si 155

'I E

is 5=

I:

5 si'

!g; I!

lI

[*! l5 l{j 5

c a

S I

d i!I

~

E 5:!i l

l i -

E j

j

=

s c

i T

i T

i 5

e6

,e j

g u

i s

-I a-z i

n-

li m

B g

. #1 I

l F' ig g

ag t{

a!!

B,i B,

I s5

[r i

I:

[is l!E

_5:

v i~

EE I;

1 Ii

!si "E2

,ta e

=

rz

~

i ag Eg B:

Eng Bir E

sl E

I l

T I

I I

.at I

f l

h

~

L i

3 E

E 5

a 31 3-1 ij igs si,i Il IE!

il n

U i

!!i la a

i r

e af 5:

g

I l

ga 3,5 i

Il

!ji E

I i

1 i

b J

REVISED 3

l

_., _ _. _, _ _ _ -. _ ___ ___ _- 7

~

Upcoming GP Courses and Workshops Date Courx Title Fee Location Sept.913 Principles ofInstructional Design:

8750 Columbia. MD instructor Trairung !!

Sept 9-20 litroduction to Microprocessors 81.700 Unfield, I A *-

I k

Sept. 9 20 Process Measurement Fundamentals s1.700 udeld PA[

5eptIl13 Designing Instructional Programs 8450 Columbia. MD Usmg)TA Data p

e o

Sept 1618 Emironmental Regulation for Fossil s450 Columbia. MD Fuct Utilities Sept 16-20 Nuclear Power Plant Technology for 8675 Columbia. MD Emergency Planners i

Sept 16-20 Adonced Operstor Trairing 8770 Colurnida. MD Sept 18 20 Applied Human Factots'in Power Plant s650 Colur'nbit MD Design and Operations Sept 23-27 ASME 5ection XI Insersice Inspection (ISI) 8715 Columbit MD Programs: Detlopment and Implementation Sept 23 27 PICK DATA /MSIC Programmer

~ sS00 Columbia. MD Sept 23 Oct. 4 Process Control Fundamentals 81.700 UnSeld, PA Sept 23.Oct. 4 Basic Electricity sB50 Udeld, PA Sept. 30-Oct 4 Health Phpics Fundamer.:a!s 8800 Columbia. MD Sept 30-Oct 25 Control Room Operator Training 88.000 Chattanooga.TN Sept. 30-Noc.1 Electricity and Electronics s4.250 UnSeld.PA Fundamentals Program

. Oct. 7 6 Special Topics in Health Phpics s300 Columbia, MD 1

Oct. 7 9 Measurement of Practical $ki!!s

$4 5 Columbia. MD i

Oct 711 Radiation Protection 8600 Cnlumbia. MD Oct hl Solid State Fundamentals 8850 Udeld FA Oct. 7 IS E!cetronic Measurement and Control 81.700 bdcld. PA Appheations Oct 8-10 Nucicar Quahry Anurance Program 8500 Chattanooga. TN Oct 911 Test Dorlopment-Ecaluating 84 5 Columbia. MD Cognitne Learnirig Oct 14 IS

!EEK Programmer Training 1500 Columna MD Oct let8 Solid Staic Doices 8550 Unfield. PA Oct 14 18 Fire Brigade Leadership Training 8695 College Park. MD Oct 14 18 Mitiganng Resoor Care Damage ( B41L) 5600 C6umNa MD Oct 15 16 Fundamentals of Procedure Writmg se0 Columna. MD Oct 21-25 FundamentalInstrument Electronics 8F50 t.anf.s id. PA Oo 2125 Adonced Operator Training 17 0 Ldcid. PA I

6ct 2325 Fundamentals of Classroom Instruenon 3*50 CntumNa MD Intiructor Trammg i Oct 2125 1:eic Instrucuonal Tet'hniquet 8550 Co?umNs. MD In<tructor Training till citi 2125 PWit Indocinnation Courw IiN eo Columna. M D cact 21 %n 'l Pneumatic Mesurement and Cunirol 81.*O0 IJefitid. PA l

Ag'pbcanons N: > %4 1

%cicarbeenung I*Au Columna MD 1

• s: 2 - %,. 1 D,gmi (s.gis runsi pis s.- (n I.:Pl.. id PA l

t t.'= %.s i

Mangaimg Rescent Curs Damagt (l'WR.

8t a.

Ce non.Na MD t.n,'.. %.s 3

. PICK Optrater p.utem i ser iSto t...:mt :a MD e

• * = '

. * *,s..A n ysc*,ar. n al. :a.h...nra. r I sans s 17. rl., lun o.,o h.1

..s os'**

t e s D.

e

'. * <. t,, ? *;

ORDER TODAY e 30-DAY MONEY BACK GUARANTEE e CALL 803 HEALY TOLL FREE 1-800-638 3838 A3 O L-,,,g% -=

w --

. mM,,,PJQ

- e 4.,. +.

nesticasaler,

.m g

.~ p r r.:

1:. :; ---n;eed,,,,

, i,1g -

" + D k.._

}.

l l

fluid Row gendamesmans 6 _,

+hc

>g 9,,

%mwm.a f

e_

y,eee.ay L

.W 1 :

=ag;,- + g.pt.wr.:.<.

t rN-u

. g, m

..u 7

]

9'N,O,y y

,p J tp p

,,, M I

g i

4 h

i y, %n

-,w.w.~

c = -

1 y ni fl_-

I i

4.

=

I i

y ge

-.p.

.t_-

c - x%x u.

e w:, -m Nuclear Power Plant Academic Program Nuclear Power Heat Transfer, introduction to PWR 5 team and Mechanical for Nuclear Power Thermodynarnics, Nuclear Power Plants

{j,,d,",([*j,,.

and Fluid Flow Fundamentals Plant Personnel Fundamentals k_,,,,,,,,

A must-have 8er utairy perwaael lk'd 'n the pubi c informauen pre.

g Complete emrv4nel tramir:s for teclimcal and somechnica' TLprepanng for NRC reactor op-grarra d over 100 mJiuck More p,,gg,,, po,,, p,,, ogg,, ion wnnel uith link cs no knowledge c8 g

penonnel for both P% R and B%R erator enams BWR and P% R wcr.

than 200 000 copia W L and others emerested in ther en.

P%h piants Leuon plarm are also asaJa-sions asaf.able QuuzeL caamL o-Psperback: 54.25 pneenn pnnciples Lesen plant Looseleaf: 57).00 l tse. ingwre abovi pnce ercise solisuons and lenon plans are ISBN 0-87681299-0 esercne muons stio a.aaabic. *-

274 pp ISBf. 0-87681 247 4 i

81w avaaable. mawre about pnce omre show pna j 12-sois.: 579.50 1080 pp,ISBN 0 87681300-8 4-volu 5295.00 tooseleaf: 575.00 l

About 1750 pp.

372 pp.,ISBN 0-876810301 l

BWR: ISBN 0-87683-144-7 PW R: ISBN 0-87681145-5 l

I l

-m w,-

_,gg-massa 88ns.acroc FULwth. _q naacio,.

1 a

a g

wS*r Inou c-a.

.n ca-ase

e.. - M. -

-c

n.,

-e 3'

'd-e:.~&)

c,v.

A.:

% a ^.:, ~

.,...r

? eme s.o.n *

'ia> N 1

J. L..-J-

- aiNYiA s t

i

, n,,jg,3 l

'~y vm:.h

.-p Mr e V

.. g

&;s.W

.g..

g k

(

L..

^

Q l

-s I

?.:

E u-i

[

5 g W ". _... q &

4 S

l.

e

>i

- f L,,

l

.. ; r-,.-- me w'_

L Introduction to B'.'.Tt' Mitigating Reactor Mitigating Reactor Practical Nuclear Reactor Theory Nuclear Power Plants Core Damage - BWR Core Damage - P%Tt Power Plant Course Technology solid mirod.cuon to boihng teamred by the NRC as required by the NRC as pg,

. sic, res,~s re ser :=t:n>

fo.c.d 04 Ti.,e ure istousn of the twee. Mile t-mor anyone imetested e n cnear penannet covenng topia fran ciam or maimenance pe sonnel Isla nd invest;gauc.t litand invesugations C power piam do gn. construcion, aiomic and a. clear urucime throtish looseleaf: 575.00 looseleaf 595.00 Looseleaf 595.00 o' operauen PWR operaung characiersucs 234 pp.,ISBN 0-87681298 2 506 pp-ISBN 0-87683-0700 424 pp.,ISBN 0-8768L077-7 2 vols.:5149.50 Lason notes: 569.50 i

i tesson plans: 51.995.00 Lnson plans: 51.995.00 694 pp.,ISBN 0 876812954 706 pp lSBN 0-8768L2484 ISBN 0-87681076 9 ISBN 0-8768L078 5 Lesson plans: 595.00 i

r g

ISBN 0-87683 249-4 g

l-_.

I;t%%t@Wf=MA M U MN D M no ieh L9%uicQ5&NG.

l caactor

'{"

S _~ w tied Ba. man l' actors e.wi w me =

-s e....s - - -~.u Apfevrer Plant Design U.*.%=

r%ane Maiertals f."f,,[N ',Id'l 1 Meb

',T,,.,

I

}

in l

'O,.

m2 and Operation 13

.y g.y c.g c.q,-

a

'pc

. /

,,-...c...e,

' : : :-.. n i.,,.

g.-

i,

4Wf

'l

"'~'*

VM

!Df$

\\

A L

Yh%

• * ~ ~ ~

~

5 D

m

,_-_.m mm, l

l Rcactor Plant Transient Response Applied Human Behavioral Science Manager's Guide

, Materials Video Training Factors in Power and Human Factors to Using the Procram Plant Design and in Power Plant Organization 1

L i n-d..grai,,, a, C)peration Applications end Performance ca.n. !.Ju

.r..ed piam en.

^ ri a 4 udm.pn demonurai-Anitude sumey J

'j gessiv vie..er p opene g mare.

fi ng,mprum remnie charac.

linee.neg hvenan facion regr pr sener rd.ni MNmnal unh A pp nng prmcipici no nocicar A supermory managens' T P80' *5 '" ":' '*r' 2"

, r h recuerwd thermal sh sL.ek i<r,uo d awicar p=ct plants lear $eleaf: 575.00 B% R set: $2.495.00 pn= er N.m oc.gn and on rauon reyvm+ hic s r aun. des s'cui iheir =ork aru J f 27J pp.15HN O.8768L2911 ISBN o.k76A3-06L7

2. solu S120.00 Comb bound paper: 549.50 rde mann 1

i Len plans: 5595fs0 PM R % : 52.495 00 418 pp.. lSBN 0-876Atl412 140 pp.. ISBN 0-876RLl40-4 Paper: 516.50

% pp.. ISBN 0 8%R3 380-6 15RN 0.N76ML29J.X ISBN 0 87683-0694

o

}NERAL PHYSICS CORPORATION 03-84-075-02 SAFETY TECHNOLOGY PROGRAM FOR t.

INSTRUCTIONAL SYSTEM DEVELOPMENT 03-84-077 'JO DEVELOPMENT AND EXECUTION OF A TEAM TRAINING i

GUIDELINES HORKSNOP 04-82-005-10 TASK ANA(YSIS OF NUCLEAR POWER PLANT CONTROL ROOM CRENS 04-84-125-t0 APPLTCATION OF TASK ANALYSIS OF NUCLEAR POWER i

PLANT CONTROL ROOM CRENS 05-84-163-00 ADVANCED NEALTH PHYSICS TRAINING COURSE t

f O

C 2

t a

g e

.