ML20027A806

Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4, Technical Evaluation Rept

ML20027A806
Person / Time
Site:	Crystal River
Issue date:	06/30/1982
From:	SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY
To:
Shared Package
ML20027A807	List: ML20027A806
References
CON-NRC-03-82-096, CON-NRC-3-82-96, TASK-1.A.2.1, TASK-2.B.4, TASK-TM SAI-186-029-29, SAI-186-29-29, NUDOCS 8207020299
Download: ML20027A806 (14)

Text

.

5AI-186-029-29 TECHNICAL EVALUATION REPORT IMPPOVEMENTS IN TRAINING AND REQUALIFICATI0t; PROGRAMS AS REQUIRED BY TM' ACTION ITEM 5 1.A.2.1 AteD 11.B.4 for the Crystal River Unit 3 (Docket 50-302)

June 30, 1922 Prepared By:

Science Paplications, Inc.

1710 Goodridge Drive McLean, Virginia 22102 Prcoared for:

U.S. r;aclear Regulatory Commission

's'ashington, D.C. 20555 Cor.t ra:t f;RC-03-82-096 J

^ 57 xe Scie 9Ce ApchCatrons. Inc kN p

TABLE 0F CONTENTS.

Section M

c I.

INTRODUCTION........................

1 II.

SCOPE AND CONTENT 0F THE EVALUATION.........

1 A.

I.A.2.1:

immediate Upgrading of R0 and SRO Training and Qualifications 1

B.

II.E.4:

Training for Mitigating Core D tmage..

6 III.

LICENSE: SU B:4 I TTAL S.._. _._._._. _.., _....... ;. _.

7

.....m_

L IV.

EVALUATION..................... '..

8 A.

I.A.2.1:

Immediate Upgrading df RO and SR0 Training and Qualificatiort-8 I

E.

II.B.4:

Tr2ining f or Mitigating Core Dnaga..

-10 V.

C ON C L U S 10:G............ '.... '.!'

10 VI.

REFEREri:EE.......................

12 1

f g

~J i

I.

INTRODUCTION' Science Applications, Inc. (SAI), as technical assistance contractor to the U.S. Nuclear Regulatory Commission, has evaluated the response by-Florida Power Corporation for Crystal River. Unit 3 (Docket 50-302) to certain requirements contained in post-TMI Action Items I.A.2.1, Immediate Upgrading of Reactor Operator and Senior Reactor Operator Training and Qualification, and II.B.4, Training for Mitigating Core Damage.

These requirements were set forth in NUREG-0660 (Reference 1) and were subse-quently clarified in NUREG-0737 (Reference 2).*

Thb purpose of the evaluation was to determine whether the licensee's operator training and requalification programs satisfy (TAC) the requirements. The evaluation pertains to Technical Assignment Control System numbers 44151 (NUREG-0737, I. A.2.1.4 ) and 44501 (NUREG-0737, I I.B.4.1 ).

As delineated below, the evaluation covers only some aspects of item I.A.2.1.4.

The detailed evaluation of the licensee's submittals is presented in Section IV; the conclu: ions are in Section V.

II. SCOPL AND CONTENT OF THE EVALVATION A.

I.A.2.1:

Imnediate Uc;radire of R9 and SRO, Training and Qualifications The cl3rification of TM1 Action Item I.A.2.1 in NUREG-0737 incor-porates a letter and f our enclosures, dated f(arch 28, 1980, from Harold R.

Denton, Directcc, Of fice of Nuclear Reactor Regulction. USF.C, to all power reactor apolicants anJ licer. sees, concerning qualifications of reactor operators (hereaf ter refer red to as Denton's letter).

This letter and enclosures imposes a number of training requirements on power reactor licensees.

This evaluation specifically addressed a s bset of the require-ments stated in Enclosure 1 of Denton's letter, namcly: I tem A.2.c, whi ch relates to operator trainir.g requirements; item A.2.e, which concerns instructor requalification; and Section C, which addrestes operater requali-ficaticq. Some of these requiremcnts are elaborated in Enclosures 2, 3, anc 4 of Denton's letter.

The training requirements under evaluation are sum-i marized in Figure 1.

The elaborations of these re;uirecents in Enclosures i

2, 3, and 4 of Denton's letter are shown respectively in Figures 2, 3, and l

4.

As noted in Figure 1, Enclosures 2 and 3 indici.t2 minimum require-ments concerning course content in their resoective areas. In addition, the Operator Licensing Eranch in NRC has taken the",positicu (Refe ence 3) tut, l

• EnclWsFe 1 of huREG-0737 and hRC's Technical Assistance Contrc. Syste n l

distinguish f our sub-actions within I.A.2.1 and two sub-actions within I I.B.4.

These subdivisions are not carried forward to tae actual presentation of the requirements in Enclosure 3 of NUREG-0737 If they had been, the items of concern here would.be contained in I.A.2.1.4 and II.B.4.1.

1 i

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CONTRO' MAh!PULAT10h3 Plant or reacto* staetscs to include a range that reactivity feedback from nuclear heat addition is notices *!e aad heat.: rata is estantished.

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• 5 tarred iten ts te perf oir.co ane.uai'y. all otaers ciennially.

5 s

g the training in mitigating core damage and related subjects should consist of at least 80 contact hours

• in both the initial training and the requali-fication programs.

The NRC : considers thermodynamics, fluid flow and heat transfer to be related subjects, so the 80-hour requirement applies to the combined subject areas of Enclosures 2 and 3.

The 80 contact hour criterion is not intended to be applied rigidly; rather, its purpose is to prrvide greater assurance of adequate course content when the licensee's training courses are not described in detail.

Since the licensees generally have their own unique course out-lines, adequacy of response to these requirements necessarily depends only on whether it is at a level of detail comparable to that specified in the enclosures (and consistent with the 80 contact hour requirement) and whether it can reasonably be concluded from the licensee's description of his train-ing material that the items in the enclosures are covered.

The Institute of Nuclear Power Operations (INPO) has developed its own guidelines for trainingrin the subject areas of Enclosures 2 W3.~

These guidelines, given in References 4 and 5, were developed in response to the same requirements and are more than adequate, i.e., training programs based specifically on the complete INP0 documents are expected to satisfy all the requirements pertaining to training material which are addressed in this evaluaticn.

The license <Tiesponse concerning increned emphasis on tran-sients is considered by SAI to be acceptable if 'it makesMexplicit reference to increased emphasis on transients and gives some indication of the naturs of the increase, or, if it addresses both normal and abnormal transients (without necessarily indicating an increase in emphasis) and the requalifi-cation program satisfies the requirements for control manipulations, Enclo-sure 1, Item C.3.

The latter requirement calls for all the manipulations listed in Enclosure 4 (Figure 4 in this report) 'to be performed, at the f requency indicated, unless they are specifically not applicable to the licensee's type of reactor (s).

Some of these manipulations may be performed on a simulator.

Personnel with senior licenses may be credited with these activities if they direct or evaluate control manipulations as they are performed by others.

Although these manipulations are acceptable for meet-ing the reactivity control manipulations required by Appendix A paragraph 3.a of 10 CFR 55, the requirements of Enclosure 4 are more demanding. requires about 32 specific manipulations over a two-year cycle while 10 CFR 55 Appendix A requires only 10 manipulations over a two-year cycle.-

s B.

II.B.4:

Training for Mitigating Core Da' mage o

item !!.B.4 in NUREG-0737 requires that "shif t technical advisors and operating personnel from the plant manager through the' operations chain to the licensed operators" receive training on the use of installed systems to control or mitigate accidents in which the core is severely dar. aged.

• A contact hour is a one-hour peried in which the course instructor is present or available f or instructing or assisting students; lectures, seminars, discussions, problem-solving sessions, and examinations are considered contact periods.

This definition is taken from Reference 4.

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. 'of Denton's letter provides guidance on the content of this training. " Plant Manager" is here tGen to mean the highest ranking manager at the plant site.

For licensed personnel, this training would be redundant in that it is also required, by 1.A.2.1, in the operator requalification program.

However, ll.B.4 applies also to operations personnel who are not licensed and are not candidates for licenses. This may include one or more of the highest levels of management at the plant. These non-licensed personnel are not explicitly required to have training in heat transf er, fluid flow and thermodyr.amics and are therefore not obligated for the full 80 contact hours of training in mitigating core damage and related subiects.

Some non-ope-ating personnel, notably managers and technicians in instrumentation and control, health physics and chemistry departments, are supposed to receive those portions of the training whicn are commensurate with their responsibilities.

Since this imposes no additional demands on the program itself, w; dc riot address it in this evaluatiori, it would be appro;riate for resicent inspectors to verify that non-operating personnel receive the proper training.

The re::uired implementation dates for all items have passed.

Hence, this eveluatiet did not address the dates nf implementation.

Moreover, the evalustion dccs not cover training program' modifications that might have been mece fcr other reasons subs 6quent td: the response to Denton's letter.

111. LICENSEE SUBf:ITTALS The licersee (FPC) has submitted to NRC a number of items.

(letters and various attachments) which explain their training and requalification programs. These submittals, made in response to Denton's letter, f orm the infor matier. base.f or this evaluation. For the Crystal River Unit 3 thcre were 31.sbmittals with attachments, f or a total of 5 items, wnich are listed below.

1.

Letter from J.A.

Hancock, Assistant Vice President, Nuclear Operations, Florida Power Corp.,

to P.F. Collins, Chief of Operator Licensing Branen, NRC.

September 15, 1980.

(2pp).

(re: Response to NRC letter' dated

' March 28, 1980).

2.

Letter from p.Y.

Baynard, Manager of Nuclear Support Services, Florida Power Corp., to D.G.

-f Eisenhet, Director of Division of Licensing, NRC. December 31, 1980. (1 pg, with enclosures.

NRC Acc. No: 8101050285.

(re: Transmittal, status of implementation and submittal schedules for the training programs).

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3. to ltr. dated 12/31/80. (2 pp, attached to item 2).

(re: Proposed topics covered in the Training Program for Mitigating Core Damage).

4.

Letter from D.G. Mardis, Acting Manager of Nuclear Licensing, FLORIDA Power Corp., to J.F. Stolz, Chief of Operating Reactors Branch #4, Division of Licensing, NRC.

May 5,

1982.(3 pp, with enclosure: item 6). NRC Acc No: 8205110624.(re:

Response to NRC's RAI dated April 1,1982).

5.

" Course Outline, Degraded Core Training". Undated.

(32 pp, attached to item 5).

IV. EVALUATION SAI's evaluatice cf the training programs at Florida-PoweTT5rpo-ration's Crystal River l' nit 2 is presented below.

Section A addresses TMI Action Iten 1.A.2.1 and presents the asscssment organized in the manner of Figure 1.

Section B addre:.:e> iM' Action Itcm I I.B. A.

A.

TMI Actier: I tem 1.A.2.1:

Upgrading of Reactor Ooerator and Senior Rea:tcr Ooerator Trair.ing and Rcmlification Programs.

.--,!tenA.2._cM The basic requirements arc that the training programs given to reactor operator anJ senior reactor operator candidates cover the subjects of heat transfer, fluid flov. anJ thermodynar.ics at the level of detail specified in Enclosure ? of Dentcn's letter.

In submittal item 1 the licensee stated that these recuirements were being incorporated it their training Droqrams.

No additional details were provided with that subT.ittal. Later, in submittal item 4, the licensee stated that the material taught on heat transfer, fluid flow and thermodynamics is comparab'e to the recairements of Enclosure 2 o' Denton's letter. This meets the.NRC requirements f or operator training in these technical areas.

..ItemA.2.c(U The requirements are that the tra'.ining prograr:s for reactor and senisc reactor operater canficates cover the sut> ject of accidert mitigation,

at the level of detail specified in Enclosure'3 of Denton's letter (see' Figure 3 of this repert).

~1 The licensec stated in submittal item 1 that they were pr'eparing an accident mitigation course along the IriP0 guidelines.

In submittal item 2, the licensee stated that they had developed a training program for mitigating core damage and they provided an outline of the tooics covered in phase one of their program. In submittal item 5, the licensee provided a more detailed outline of its training program.

SAI has reviewed both B

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l outlines and, while titles do not directly correspond with that of Denton's, it appears that the necessary material is covered by the program. This is in agreement with the licensee's assertion stated in s 5mittal item 4.

The licensee stated in submittal item 4 that the training program involved 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> in the areas of heat transfer, fluid flow, thermodynamics and accident mitigation. This does not meet the NRC criterion of 80 contact hours for tnese subjects.

Encloture 1, Item A.2.c(3)

The requirement is that there be an increased emphasis in the

-training program on dealing with reactor transients.

In submittal item 1, FPC stated the training program involved an increased emphasis on reactor and plant transients and also stated that this program element would be continually upgraded.

This part of the FPC training program complies with the NRC requirements., Item A.2.e The requirement it that in;tructors for reactor operator t*aining prograas b2 enrolled in ap;mopriate requalification programs to assure they are cognizant-c' current opera:in; history,,. problep;,s and changes to precedures and ad;.dr.istretivc limit at ions.

In submittal ite-1, FFC stated that licensed nuclear operations instructors and supcesisors are enrolled in the aperatur requalification program.

In submite.al item 4, the licensee specifically stated that the instructor requalification program does address c.urrent operating history, problems and changes in nrecedures and administrative limits. This program f or licensed instructor; meets the hRC requirements. _Ites C.!

1 The primary requirement is that the requalification programs have instruction in the a.reas of heat transfer, fluid flow, thermodynamics and accident mitigaticr..

The levcl of detail required in the requalification program is tnat of En:losures 2 and 3 of Denton's letter.

In addition, these instructions must involve an adequate number of contact hours.

The same submittal items ' hich provided inf'ormation relative to w

items I.A.2.c(1) and I.A.?.c(2) ebo<e (submittal, items l', 2 and 4) contained information about the heat transfer, tluid flow, thermodynamics and accident-mitigation aspsects of the opeiator requalification program. These progran elements are judged to meet the NRC requirements.

Also as discussed in item I.A.2.c(?) the time devoted *UD the program elements of heat transfer, fluid flow, thermodynamics and accident mitigatien is 56 contact hours.

This does not meet the r3C criterion of 80 contact hours for these subjects.

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., Item C.?

The requirement for licensed operators to participate in the accelerated requalification program must be based on passing scores of 80%

overall, 70% in each category.

In submittal item 4, the licensee stated that the requalification program calls for accelerated requalification if the overall score is less than 80% and if the score in any category is less than 70%. Tais meets the NRC requirement., Item C.3 TM1 Action Item I.A.?.1 calls for the licensed operator requalifi-cation program to include perf ormance of control manipulations involving both normal and abncemal situations. The specific manipulations required and their perf orrrance f reqJency are iaentified in Enclosure 4 of the Denton letter (see Figure.4-of this report).

In submittal item 4, FPC stated that the operator requalification program does call for control manipJlations es specified in Enclosure 4 of Denton's letter.

This meets the f4RC requirement for control manipulations as a part of operator requalification.

B.

II.B.4 Training-for Mitigating Core Dameg Item II.S.4 requires that training for' mitigat'iiig core damage, indicated in Enclosure 3 ef Denton's letter, be given to shif t technical advisors and operating personnel f rem the plant manager to the licensed operators. This includes l'oth licenss) and non-licensed persenne!.

The requirement for training licensed personnel is partially met as a result of the licensee's actions discussed under Action Item I A.2.1.

The training prugram covers the reqaired material (Enclosure 3 of Denton's letter) but 80 contact hours are not involved in the instruction of accident mitigation and related subjects such as heat transfer, fluid flow and thermodynamics. The licensen stated in subnittal iten 4 that 56 contact hours are involved for these subjects.

The requirement for training non-licensed operating personnel and shif t technical advisors is met at Crystal River Unit 3.

This conclusion is based on information provided in submittal item 4 which listed the titles of personnel trained and inf ormation provided in reference 7 which relates these titles to an organization structure'.

e p

V.

CONCLUSIONS SAI has reviewed the submittals of Florida Power Corporatics about their training and requalification program relative to TM1 Action Plan Item 1.A.2.1 and II.B.4 and made evaluations on the content of these programs.

SA! has found that FPC meets the requirements of TMI Action Item I.A.2.1 with the exception of not having 80 contact hours devoted to the subjects of heat transfer, fluid flow, thermodynamics and accident mitigation during each of the initial training and requalification programs 1

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The requirements for TMI Action Item II.B.4 are met with 'the exception that 80 contact hours are not involved with the accident mitigation training of licensed personnel. The training of non-licensed personnel and shift technical advisors meets the NRC requirements.

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V.

REFERENCES 1.

"NRC Action Plan Developed as a Result of the TMI-2 Accident." NUREG-0660, United States Nuclear Regulatory Commission. May 1980.

2.

" Clarification of TMI Action Plan Requirements," NUREG-0737, United States Nuclear Regulatory Commission. November 1980.

3.

The NRC requirement for 80 contact hours is an Operator Licensing Branch technical position.

It was included with the acceptance criteria provided by NRC to SAI for use in the present evaluation.

See letter, Harley Silver, Technical Assistance Program Management Group, Division of Licensing, USNRC to Bryce Johnson, Program Manager, Science Applications, Inc.,

Subject:

Contract No. NRC-03-S2-096, Final Work Assignment 2, December 23, 1981.

4.

" Guidelines f or Heat Transfer, Fluid Flow. and Thermodynamics Instruction;" STG-02, The~ Institute ~ of Nuclear ~h'wer Operations.

December 12, 1980.

5.

"Guidelincs fer Trair. ire to Reccgnize and Mitigate the Consequences of Core Damage," STG-01, The Institute of Nuclear Pov.er Ope'ations.

January 15, 1931.

6.

I & E R e p o r t~.'io. : 50 202/81-15, Office cf Inspection & Enforcement, NR C.

Approved by V.L. Brownlee, Acting Chief,; Reactor Projects Section 28, D i '. 4 s i o n of Resider.t F. Peactor Freject inspection, September 24,1931.(f,0. of pages, unk now n). NRC Acc No:

5112310317.

(re: Verificttitn of the i.nalemen tation of tr.e t rainir.g programs required by GUREG-073/, Itens I.A.?.1(4), & I I.E.4.? A ).

7.

Letter dated January 19, 1982, f'cm David G. Mardis, Flcrida Power Corporation to Harold R. Denton, U.S. NRC, Technical Specification Change r,equest No. 67, ilev.1.

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