ML19332A729

Forwards Operator Licensing Branch Input to SER for Full Power Operation

ML19332A729
Person / Time
Site:	Salem
Issue date:	09/11/1980
From:	Moore V Office of Nuclear Reactor Regulation
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 8009180170
Download: ML19332A729 (13)

Text

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?j MEMORANDLH FOR:

A. Schwencer, Acting Chief. Licensing Branch No. 3, s

Division of Licensing, NRR s

1 FROM:

Y. A. Moore, Acting Deputy Director, Division of i

Hinan Factors Safety. !!RR j

SUDJECT:

TMI MTSTA?IDING ISSUES, SALEM flVCLEAR GENERATING S

STATION, UNIT #2 1

e i

lhe attached material regarding trainir:g is transmitted for enclosure j

in the Salen Nuclear Generating Station, Unit 2 SER for Full Power Operation. This review was perfonned by Kevin R. Mahan of the Operator i

Licensing Branch.

i V. A. floore, Actino Deprity Director Division of Htnan Factors Safety Office of fluclear Reactor Regulation b

, CONTACT:

/

K. R..Mahan

./

X27476 1

Enclosure:

E as stated above j

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DISTRIBUTION:

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NRC F_OR_M 31, (9 76) NRCM.0240 M U.S. GOVERNMENT PRINTING @FFt8@s B979 2,9 369

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~1'3. 0 Conduct of Operations 7

13.2 Licensed Operator Training Program

(

The infonnation contained in h'JREG-0517, SER for the Salem Nuclear f.

Generating Station, Unit 2, thru Supplement No. 4 remains valid.

h i

Standard Review Plan 13.2, Training, was used in the review, e

Regulatory. Guide 1.8, Selection and Training of Personnel and 10 CFR 55.20 through 55.23 and 55.25 were used to evaluate the

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Programs, i

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Part I - Fuel-Inading and Iow-Power Testing Requirements i'-

II.B.4' TRAINING FOR MITIGATING WRE DAMAGE E

POSITION

[

'Ihe staff requires that the applicant develop.a program to E

l ensure that all operating personnel are trained in the use E

of installed plant systems to control or mitigate an accident in W ich the core is severely damaged. 'Ihe training program shall include the following topics:

5 A.

Incore Instrumentation l

1.

Use of fixed or novable incore detectors to deter-F l

mine extent of core damage and geometry changes.

+

2.

Use of thermocouples in determining peak tenperatures; nnthods for extended range readings; unthods for direct readings at-terminal junctions.

1 B.

Excore Nuclear Instrunentation (NIS) 1.

Use of NIS for determination of void information; void location basis for NIS response as a function of core temperatures and density changes.

~

C.

Vital Instrumentation

-1.

Instrumentation response in an accident environment; i!

failure sequence (time to failure, nethod of failure);

indication reliability (actual vs indicated level),

q-i

2.

Alternative nuthods for neasuring flws, pressures, levels, and temperatures.

a.

Determination of pressurizer level if all level transmitters fail.

b.

Determination of letdown f1w with a clogged filter (lw f1w).

Determination of other Reactor Coolant Systen c.

parannters if the primary nuthod of nuasurenent has failed.

P D.

Primarv Chemistry 3

1.

Expected chenistry results with severe core dage; k.

consequences of transferring small quantities of liquid outside contalment; importance of using leak tight systems.

2.

Expected isotopic breakdown for core damage; for cir damage, i

3.

Corrosion effects of extended imrersion in primary water; tine to failure.

'J l

i, L '

E.

Radiation Ibnitoring 1.

Response of Process and Area Monitors to severe damges; behavior of detectors when saturated; mthod for detecting radiation readings by direct reasurenent at detector output (overanged detector);

expected accuracy of detectors at different locations; use of detectors to determine extent of core damage.

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l!

2.

Methods of determining dose rate inside contain-nunt from neasurerents taken outside containment.

il F.

Gas Generation s

1.

Methods of H2 generation during an accident; other sources of gas (Xe, Kr); techniques for venting or disposal of non-condensibles.

2.

M flantrability and explosive limit, sources of 2

0 in contaiment or Reactor Coolant Systen.

2 Discussion and G nclusions Public Service Elec*.ric and Gas Company has candted to

. dram as indicated in Supplenent No. 4 to NLREG-0517 (IMI-2 Issues Related to Fuel load and Im Power Test Prograr..)

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By letter dated April 1,1980, Public Service submitted a summary of the. training material for Mitigating Core Damage.

A review of this material has indicated that all topics will be addressed and

.that training will be completed prior to full power operation.

Based on the foregoing, we have concluded that Salem Unit 2, has complied with NUREG-0694, Item II.4.B.

~i -

I.A.2.3 ADMINISTRATION OF TRAINItU PROCPAS FOR LICENSED OPERA'IORS POSITION Training instructors who teach systems, integrated responses, transients and sinulator courses shall successfully complete a SRO examination.

Instructors shall attend appropriate' retraining programs that address, as a minfrum, current operating history, problems

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and changes to procedures and administrative limitations.

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In the event an instructor is a licensed SRO, his retraining shall be the SRO requalification program.

RESPONSE

All Salem instructors that t,each systens, integrated responses, and transient courses presently hold valid SRO licenses.

Instructors participate in the applicable portions of the recualifications program.

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. ODNCLUSION

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Based on the foregoing, se have concluded that Salem, e

Unit 2 has ccuplied with NUREG-0694, Iten I. A.2.3.

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I.A.2.1 IMMEDIATE UPGRADING OF OPERATOR AND SENIOR OPERATOR TRAINING AND y

I OUALIFICATION i

i 1j POSITION

!i Applicants for SRO license shall have 4 years of responsible 1

power plant experience, of which at least 2 years shall be nuclear power plant experience (including 6 months. at the i

9 specific plant) and no more than 2 years shall be academic f

or related technical training.

l M

Certifications that operator license applicants have learned I

to operate the controls shall be signed by the highest level of corporate management for plant operation.

Revise training programs to include training in heat transfer, fluid flow, thermodynanics, and plant transients.

i

RESPONSE

Applications received for a senior operator ifcense on Salem Unit No.-2 have indicated that the required experience levels have been met.

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Certifications that operator license applicants have E

learned to operate the controls will be signed by F. W. Schneider, Vice President - Production.

The Licensed Operator Training Programs have been revised

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to include training in heat transfer, fluid flow, thermo-S

_ dynamics, and plant transients.

CONCLUSION

!?

Individuals who have received a Senior license on Salem Unit No. 2 meet all experience requirements.

Applications which. have been recently submitted are signed by the Vice President-Production. Training programs have been revised as required.

The staff (0LB) will review revised training programs in accordance with Item A.2.C of H. Denton's letter of March 28, 1980.

=

5 We conclude that Salem has satisfied the requirements of NUREG-0694, Item I.A.2.1.

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1 l

- e.

i I.A.3.1 REVISE SCOPE AND CRITERIA FOR LICENSING EXAMS h

f POSITION Applicants for operator licenses will be required to grant permission to the IRC to inform their facility managenent regarding the results of examinations.

Contents of the licensed operator recualification program r

shall be nodified to include instruction in heat transfer, fluid flow, thernodynamics, and mitigation of accidents involving a degraded core.

The criteria for requiring s licensed individual to partici-pate in accelerated requalification shall be nodified to be consistent with the new passing grade for issuance of a license.

Requalification programs shall be nodified to require specific reactivity control nunipulations. Ibraal control nanipulations, l

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_ 2._

such as plant or reactor startups, must be performd. Control

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manipulations during abnormal or em rgency operations shall be l

walked through and evaluated by a mmber of the trairdng staff.

An appropriate sirulator may be used to satisfy the requirem nts for control manipulations.

RESPONSE

Applicants for operator licenses will grant per-udssion to the NRC to infom plant managemnt regarding the results of examination.

i Content of the licensed operator requalification program has been nodified to include instruction in heat transfer, fluid flow, therrodynamics, and mit-igation of accidents involving a degraded core.

The criteria for requiring a licensed individual to participate in accelerated requalification have been nodified to reflect the new passing grade for issuance of licenses.

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I A-l The requalification, program has been t:odified to remire specific i

reactivity control manipulations as per Enclosure 4 to H. Denton's letter of March 28, 1980.

One week of Simulator Training is scheduled for each licensed operacor per year.

Control mnipula-

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tions during abnormal or emergency operations are evaluated by i

the Simulator training staff and provided to Public Service.

As mny reactivity manipulations as practical will be performed.

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at Salem; those manipulations not performed at Salem will be performed on a sfrulator.

i CONCLUSION i

Based on the information submitted by Salem we conclude that i

Salem has satisfied all requirements of NLREG-0694, Item f

I.A.3.1.

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Jesumum_ PP4 l

5 SEP 111980 c

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!E!?0RANDUM FOR:

A. Schwencer, Acting Chief, Licensing Branch No. 3,

~

' Division of Licensing, NRR FROM:

V. A. Moore, Acting Deputy Director, Division of Human Factors Safety, NRR E~

SUBJECT:

TMI OUTSTANDING ISSUES, SALEM NUCLEAR GENERATING STATION, UNIT #2 The attached material regarding training is transmitted for enclosure k

in the Salen Nuclear Generating Station, Unit 2 SER for Full Power Operation. This re. view was performed by Kevin R. Mahan of the Operator Licensing Branch.

i.

V. A. floore, Actina Deputy Director Division of Human Factors Safety Office of Nuclear Reactor Regulation C^TTACT:

K. R. Mahan 4

X27476

)

~

Enclosure:

as stated above DISTRIBUTION:

OLB R/F OLB F/F NRR R/F Central Files TERA fSIC KR Mahan JJ Buzy JD Kerrigan PF Collins VA floore e

8 8091$ 0 ' 170 g

l OLB :H FS OL DHF5...

OFFICE SURNAME DATCk..

NT C FORM 318 (G.76) NRCM 0240 DU.S. GOVERNMENT PRINTING OFFl@E: 1979 289 369 t

A ii

~

13.0 Conduct of Operations r

13.2 Licensed Operator Training Program

• ?

The information contained in-NUREG-0517, SER'for the Salem Nuclear l

[

Generating Station, Unit 2, thru Supplement No. 4 remains valid.

h

^

Standard Review Plan 13.2, Training, was used in the review.

Regulatory Guide 1.8, Selection and Training of Personnel and 9!

10 CFR 55.20 through 55.23 and 55.25 were used to evaluate the programs.

t l

-I i

.. 1 l

. 1 L

l.

-Part I -' Fuel-Ioading and Iow-Power Testing Recuirments II.B.4 TRAINING FOR MITIGATING CORE DAMAT.

POSITION The staff requires that-the applicant develop a program to 9

ensure that all operating personnel are trained in the use of installed plant systes to control or mitigate an accident in which the core is severely. damged. The training program shall include the following topics:

4" A.

Incore Instrucentation 1.

Use of fixed or novable incore detectors to deter-mine extent of core damage and geometry changes.

2.

Use of thermocouples in determining peak tmperatures; nethods for extended range readings; methods for direct readings at-terminal junctions.

i B.

Excore Fuclear Instrumentation (NIS) 1.

Use of NIS for determination of void information; void location basis for NIS response as a function of core temperatures and density changes.

C.

Vital Instrucentation 1.

Instnnentation response in an accident environment; failure sequence (time to failure, method of failure);

indication reliability (actual vs indicated level),

,e 2.

Alternative nethods' for neasuring flows, pressures,

-levels, and temperatures.

a.

Determination of pressurizer level if all level i-transmitters fail.

i.

l b.

Determination of letdown flow with a clogged ei filter (low flow).

=

Determination of other Reactor Coolant Systen c.

2}

parameters if the primary method of measurenent

(.

9-has failed.

i

i i

D.

Primary Chemistry E-1.

Expected chemistry results with severe core damage; g

consequences of transferring small quantities of 3

liquid outside contaircent; importance of using

[

1eak tight systems.

2.

Expected isotopic breakdown for core damage; for clad damage.

E E

.3.

Corrosion effects-of extended innersion in primary water; time to failure.

w L

t

---

..w..-.-

p g-

- ?

9:

5 I

?

s; E.

. Radiation Monitoring 3-S-

1. -

Response of Process and Area Monitors to severe i.

g damages; behavior of detectors When saturated; E-method for detecting radiation readings by direct i

measuremnt at detector output (overanged detector);

expected accuracy of detectors at'different locations; use of detectors to determine extent of core damage.

1. i

[.

2.

Methods of determining dose rate inside contain-Uent from measurements taken outside cor 'inment,

j-j F.

Gas Generation

)

1.

Methods of H2 gener tion during an accident; other j

sources of gas (Xe', Kr); techniques for venting I

~

or disposal of non-condensibles.

u i

3 2.

H flammability and explosive limit, sources of 2

b 0 in containment or Reactor Coolant System.

2 6

Discussion and Conclusions Public Service Electric and Gas Company has commited to C.

this program as indicated in Supplement No. '4 to hTREG-0517

-(TMI-2 Issues Related to Fuel Load and Iaa Power Test Program.)

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y e

p

!' i F

j l

j.,

By letter dated April 1,1980, Public Service submitted a summary

'of the training material for Mitigating Core Damage. A review of this material has indicated that all topics will be addressed and that training will be completed prior to full power operation.

. Based on the foregoing, we have concluded tbst Salem Unit 2,_ has complied with NUREG-0694, Item II.4.B.

i b

9 s.

n

'I.A 2 3' ADMINISTRATION OF TRAINING PROGRAMS FUR LICENSED OPERATORS POSITION l

. Training instructors who teach systems, integrated responses,

~

transients and sinulator courses shall successfully complete a SRO examination.

Instructors shall attend appropriate retraining programs that address, as a mininum, current operating history, problens and changes to procedures and administrative limitations.

In the event an instructor is a licensed SRO, his retraining shall be the SRO requalification program.

i

RESPONSE

All Salem instructors that teach systens, integrated rest onsec, and transient courses presently hold valid SRO licenses.

Instructors participate in the applicable portions of the requalifications program.

E

'I

7 I l Based on the foregoing, w have concluded that Salem, CONCLUSION Unit 2 has ccuplied with NUREG-0694, ktem I. A.2.3.

i F

E M

9 b

0 4

d k

6 N

I i

f_

' I.A.2.1 IMMEDIATE UPGRADING OF OPERATOR AND SENIOR OPERATOR TRAINING AND OUALIFICATION i

?

. POSITION

~

i j

Applicants for SR0 license shall have 4 years of responsible n;

j power plant experience, of which at least 2 years shall be

f.

nuclear power plant experience (including 6 months at the i

specific. plant) and no more than 2 years sha.ll be academic g

h or related technical training.

5 4

Certifications that operator license applicants have learned

(-

to operate the controls shall be signed by the highest level s

of corporate management for plant operation.

=

4

~

Revise training programs to include training in heat transfer,

. fluid flow, thermodynamics, and plant transients.

=

F k

k

RESPONSE

Applications received for a senior operator. license on Salem Unit No. 2 have. indicated that the required experience levels have been met.

e G

S

i i:.i

. Certifications, that operator license applicants have

- learned to operate the _ controls will be signed by i

F. W. Schneider, Vice. President - Production.

The Licensed Operator Training Programs have been revised to include trcining in heat transfer, fluid flow, thermo-

, dynamics, and plant transients.

CONCLUSION Individuals who have received a Senior license on Salem Unit No. 2 meet all experience requirements.

Applications which have been recently submitted are signed by the Vice President-Production.

Training programs have been revised as required. The staff (0LB) will review revised training programs in accordance with Item A.2.C of H. Denton's lettcr of March 28, 1980.

We conclude that Salem has satisfied the requirements of NUP.EG-0694, Item I.A.2.1.

E

1

~

i L

I.A.3.1 REVISE SCOPE AND CRITERIA EDR LICENSING EXAMS i-POSITION Applicants for operator licenses will be required to grant permission to the NRC to inform their facility management regarding the results of exaninations.

Contents of the licensed operator requalification program shall be nodified to include instruction in heat transfer, fluid flow, thernodynamics, and mitigation of accidents involving a degraded core.

The criteria for requiring A licensed individual to partici-pate in accelerated requalification shall be modified to be consistent with the new passing grade for issuance of.a license.

Requalification programs shall be codified to require specific reactivity control manipulations.- Normal control nanipulations, I

O w

-~

. _ _ _ ~.

+

x:q 34 c

c

- 2.-

i-lf k-k such as plant or reactor startuas, must be performed.

ContTol p

p manipulat; ions during abnormal or errergency operations shall be 4

d by a member of the tra aing staff, p-k

.wal ed through and evaluate t

I-An appropriate sirulator may be used to satisfy the requirerents for control manipulations.

RESIUISE Applicants for operator licenses will grant per-L mission to the NRC to inform plant management s

[

regarding'the results of examination.

L 1:

Content of the licensed operator requalification program has been codified to include instruction in heat transfer, fluid flow, thermodynamics, and mit-igation of accidents involving a degraded core.

j The criteria for. equiring a licensed individual to

- participate in accelerated requalification have been nodified to reflect the new passing grade for issuance of licenses.

h-e.

dib m

~

.m.

The requalification program has been nodified to require specific reactivity control manipulations as per Enclosce 4 to H.-Denton's letter of March 28, 1980. One wek of Simulator Training is scheduled for each licensed operator per year. Control manipula-tions during abnormal or emergency operations are evaluated by the Sinulator training staff and provided to Public Service.

As nany reactivity manipulations as practical will be nerformed at Salem; those manipulations not perfortred at Salem will be performed on a sirulator.

CONCLUSION Based on the~information subinitted by Salem we conclude that

- Salem has satisfied all requireuents of NUREG-0694, Item I.A.3.1.

J i

i 9

-I i