ML20076H361

Control of Heavy Loads (C-10),Philadelphia Electric Co, Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept

ML20076H361
Person / Time
Site:	Peach Bottom
Issue date:	08/31/1983
From:	Bomberger C, Sargent I FRANKLIN INSTITUTE
To:	Singh A NRC
Shared Package
ML20076H364	List: ML20076H361
References
RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR TAC-08070, TAC-08071, TAC-8070, TAC-8071, TER-C5506-379-3, TER-C5506-379-380, NUDOCS 8309020392
Download: ML20076H361 (32)

Text

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. TECHNICAL EVALUATION REPORT 1

! i CONTROL OF HEAVY LOADS 1C-10) l l

PHILADELPHIA ELECTRIC COMPANY l

l PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 3

11 NRC DOCKETNO. 50-277, 50-278 FRC PROJECT C5506 -h NRC TAC NO. 08070, 08071 FRC ASSIGNMENT 13 NRC CONTRACT NO. NRC-03-81-130 FRCTASKS 379, 380 l 1

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l Prepared by Frank!!n Research Center Author: I. H. Sargent C. R. Bomberger  !

20th and Race Streets Philadelphia,PA 19103 FRC Group Leader: I. H. Sargent l

Prepared for

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Nuclear Regulatory Commission Lead NRC Engineer: A. Singh Washingtori. D.C. 20555 l

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This report was prepared as an account of work sponsored by an agency of the United States Govemment. Neither the United States Govemment nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any Information. appa-ratus, product or process disclosed in this report, or represents that its use by such third part/ would not infringe privately owned rights.

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. 00. Franklin Research Center A Division of Tne Franklin Institute m s.n Franan Pm. m Pa.19103 GISI ua 1000 3w

F TECHNICAL EVALUATION REPORT CONTROL OF HEAVY LOADS (C-10)

PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 3

m NRC DOCKET NO. 50-277, 50-278 FRC PROJECT C5506 NRC TAC NO. 08070, 08071 FRC ASS!GNMENT13 NRC CONTRACT NO. NRC-03-81-130 FRC TASKS 379, 380 Prepared by Frankiin Research Center Author- I. H. Sargent 20th and Race Streets C. R. Bomberger l Philadelphia, PA 19103 FRC Group Leader: I. H. Sargent Prepared for Nuclear Regulatory Commission Washington, D.C. 20555 Lead NRC Engineer: A. Singh l

l l

This report was prepared as an account of work sponsored by an agency of the United States Govemment. Neither the United States Government nor any agency thereof, or any of their employees. makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, appa-ratus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.

Prepared by: Reviewed by: Approved by:

sL u Principal Auther V lJhf d 10 mA

' Department Dl/ectorf cate- t/m /#5 cate: 'bl'1 Date: 4-N/"f9 a

. . Franklin Research Center A Division of The Franklin Institute The Bensma Frankka Parmwey Ptuta Pa. t9103 (215) us.1000 l

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TER-C550 6-379/380 CCNTENTS .

Section Title Pace 4:

1 INTRODUCTION. . . . . . . . . . . . . . 1 4

1.1 Purpose of Review . . . . . . . . . . . 1 1.2 Generic Background . . . . . . . . . . . 1 1.3 Plant-Specific Background . . . . . . . . . 2 2 EVALUATION . . . . . . . . . . . . . . 4 2.1 General Guidelines . . . . . . . . . . . 4 2.2 Interim Protection Measures. . . . . . . . . 23 3 CONCLUSION . . . . . . . . . . . . . . 26 l

3.1 Gendral Provisions for Load Handling . . . . . . 26 l

3.2 Interim Protection Measures. . . . . . . . . 26 4 REFERENCES . . . . . . . . . . . . . . 28 l

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i TER-C5506-379/380 FOREWORD This Technical Evaluation Report was prepared by Franklin Research Center under a contract with the U.S. Nuclear Regulatory Commission (Office of j' Nuclear Reactor Regulation, Division of Operating Reactors) for technical assistance in support of NIC operating reactor licensing actions. The technical evaluation was conducted in accordance with criteria established by the NRC.

Mr. I. H. Sargent and Mr. C. R. Bomoerger contributed to the technical preparation of this report through a subcontract with WESTEC Services, Inc.

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TZR-C550 6-379/380 1.

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INTRODUCTION

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1.1f PURPOSE OF REVIEW

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j y This technical evaluation report documents an independent review of general load handling policy and procedures at Philadelphia Electric Company's

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(PECO) Peach Bottom Atomic Power Station Units 2 and 3. This evaluation was l 4 performed with the following objectives o to assess conformance to the general load handling guidelines of l' ,

NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants" (1] ,

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" Section 5.1.1 l r o to assess.conformance to the interim protection measures of NUREG-0612, Section 5.3.

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• l 1.2 GENERIC BACKGROUND Generic Technical Activity Task A-36 was established by the U.S. Nuclear Regulatory Cosutission (NBC) staff to systematically examine' staff licensing criteria and the adequacy of measures in effect at operating nuclear power I plants to assure the safe handling of heavy loads and to recommend necessary changes to these measures. This activity was initiated by a letter issued by the NBC staff on May 17, 1978 [2] to all power reactor licensees, requesting l

information concerning the control of heavy loads near spent fuel.

The results of Task A-36 were reported in NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants." The staff's conclusion from this evaluation was that existing measures to control the handling of heavy loads at operating plants, although providing protection from certain potential problems, do act adequately cover the major causes of load handling accidents and should be upgraded.

In order to upgrade measures for the control of heavy loads, the staff developed a series of guidelines designed to achieve a two-phase objective

,3 using an accepted approach or protection philosophy. The first portion of the objective, achieved through a set of general guidelines identified in

, NUREG-0612, Section 5.1.1, is to ensure that all load handling systems at

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TER-C5506-379/380 nuclear power plants are designed and operated such that their probability of failure is uniformly small and appropriate for the critical tasks in which they are employed. The second portion of the staff's objective, achieved through guidelines identified in NUREG-0612, Sections 5.1.2 through 5.1.5 is

.. to ensure that, for load handling systems in areas where their failure might result in significant consequences, either (1) features are provided, in 1. '

addition to those required for all load handling systama, to ensure that the potential for a load drop is extremely small (e.g., a single-failure-proof crane) or (2) conservative evaluations of load handling accidents indicate that the potential consequences of any load drop are acceptably small.

Acceptability of accident consequences is quantified in NUREG-0612 into four accident analysis evaluation criteria.

A defense-in-depth approach was used to develop the staff guidelines to ensure that all load handling systems are designed and operated so that their probability of failure is appropriately small. The intent of the guidelines is to ensure that licensees of all operating nuclear power plants perform the followings o define safe load travel paths through procedures and operator training so that, to the extent practical, heavy loads are not carried over or near irradiated fuel or safe shutdown equipment o provide sufficient operator training, handling system design, load handling instructions, and equipment inspection to ensure reliable

, operation of the handling system.

Staff guidelines resulting from the foregoing are tabulated in Section 5 of NUREG-0612. Section 6 of NUREG-0612 recommended that a program be initiated to ensure that these guidelines are implemented at operating plants. 'i 1.3 PLANT-SPECIFIO BACKGROUND .

On December 22, 1980, the NBC issued a letter [3] to PECO, the Licensee for the Peach Botton Atomic Power Station, requesting that the Licensee review provisions for handling and control of heavy loads, evaluate these provisions

! with respect to the guidelines of NUREG-0612, and provide certain additional information to be used for an independent determination of confor: nance to

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b TER-C5506-379/380 these guidelines. On June 18, 1981, PECO provided the initial response (4) to this request, and additional information was provided by the Licensee on

, December 22, 1981 [5]. The information provided in these two responses was used to prepare a draft technical evaluation report (TER) which was issued on March 25,1982. Subsequent to the release of this TER, additional information was provided in a letter dated May 20, 1982 [6] and a telephone conversation held on September 13, 1982; the results of that conversation were documented in a letter dated October 25, 1982 [7]. Upon review of the additional information, a draf t final TER was issued on May 17, 1983 and discussed with PECO on July 19, 1983. Following this discussion, PECO provided certain additional information on August 10, 1983 [8]. Information provided by PECO in original and supplementary responses as well as telephone conversations form the basis for this final technical evaluation.

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4 TER-C5506-379/380

2. EVALUATION AND RECOMMENDATIONS This section presents a point-by-point evaluation of load handling provisions at Peach Botton Units 1 and 2 with respect to NBC staff guidelines provided in NUREG-0612. Separate subsections are provided for both tne general guidelines of NUREG-0612, Section 5.1.1 and the interim measures of NUREG-0612, Section 5.3. In each case, the guideline or interim measure is t presented, Licensee-provided information is summarized and evaluated, and a conclusion as to the extent of compliance, including recommended additional action where appropriate, is presented. These conclusions are summarized in Table 2.1.

2.1 GENERAL GUIDELINES The NRC has established seven general guidelines which must be met in order to provide the defense-in-depth approach for the handling of heavy loads.

These guidelines consist of the following criteria from Section 5.1.1 of NUREG-0612:

Guideline 1 - Safe Inad Paths Guideline 2 - Load Handling Procedures Guideline 3 - Crane Operator Training 1

Guideline 4 - Special Lifting Devices Guideline 5 - Lifting Devices (Not Specially Designed)

Guideline 6 - Cranes (Inspection, Testing, and Maintenance) l Guideline 7 - Crane Design.

These seven guidelines should be satisfied for all overhead handling '

systems that handle heavy loads in the vicinity of the reactor vessel, near spent fuel in the spent fuel pool, or in other areas where a load drop may .

damage safe shutdown systems. The Licensee's verification of the extent to which these guidelines have been satisfied and an evaluation of the Licensee's verification are containsd in the succeeding paragraphs.

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il G3 Table 2.1. Peach bottos/seueso-e612 Compliance seatsas g teelght Interim latesta 8

or Guideline ! eutdeline 2 culdeline 3 Guideline 4 Guideline 5 Guidellne 6 Guideline 7 seessure 1 8eessese 6 O Capacity Sale imod Crane Operator Special Lifting Crane - Test Technical Special gesey tuede Stonal raths procedures Teatnine Duelces Silmee end Inspection Crane Deelen Ssaec ificat ions Attention

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!. peactos 125/S - - R -- -

A C -- --

sullding Crane

a. Shlend eleg 35 C C = - C ~ == = C an. Cool Plug 40/61 C C - - C - -- C -

c. Slot plug S.5 C C - -

C - -

C -

IFuel sooll 8 d. Drywell used 6.5 C C -- B - - - -

C L's I s. my mead g6.S C C - 3 - - - -

C

f. Steam pryer 31 C C - -

C - - --

C

g. Steam sepa- $2 C C - -

C ~ - --

C gator

h. Fuel Cask 194/37.1 C C -- R - - - C -

8. Fuel Pool 3.15 C C - - C -- -

C --

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j. Fuel Pool cate eso. 2 3.75 C C -~ ~ .- ' s C -- e- C --

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k. Defueling 9 C C ~ - C - - C - gag o nnei .

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'. Ch C = Licensee action le consistent with 38USEG-0612 Caldeline. 8 R = The Licensee has proposed geetelone or aud!!lcations which, when Implemented, w!!! seestt la load hand!!ag reliability constatent mith NUMEC-Gbl2.

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$ es Guideline 1 Guldeline 2 Guideline 3 Caldeline e Guldeline 5 Guideline e Guideline 7 8eessuse i Museuse 6 d

=3 tieavy I.ca.le Capacity sete goed itqual Pa tles Psocedusee Crane eyesates st*clat Letting Tasinthe Devices Silnee Csame - Test Techedcal speciat and Insanection Cr ane Deelsen $pecl(icatione Atten g n

$ l. ressannel 4 C C - -

C - -- -- --

Basket

n. prv peed le C C -- C -- -- -- --

C Basulation

n. the ruel 4.5 C C -- C - -- - C --

Csatem

o. pgel l =ent 2 C C -- --

C -- - -

C isandtlag etattosa

p. krw-Daymell 3.8 C C -- R -- -- -- C 1 leead 5tsung-f back

q. Fuel Cask 4.41 C C -- R -- - --

C --

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s. Ieydeaulic 3.8 C C -- R -- - -- -- --

Tensiones

o. Osyes-Sepe- 5.75 C C --

R C -- -- --

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satos Silag

t. ImaJ Block 7.2 C C -- -

C --' - C C

u. aseed stud 1.5 C C -- -- C -- -- -- C 344;k

e. Ses v ece Plat- 2 C C --

A C -- -- -- C 63 form I 81

2. Turbine bldg. M Csane  !!0/15 -- -- R -- -- a C -- --

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C -- -- ... --

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or Guideline 1 Guideline 2 Guideline 3 Guideline 4 Guideline 5. Guideline 6 Guideline 7 seessuse ! seeasure 6 Capacity sete toad Csane operator special Lifting Crane *reet Techalcat special meavy toads (tone) Pathe Procedures Tsalaine Devices slinea and Inspection Cr ane pes ten specificatione attention O b. Gen. Outer 44 C C - - C --

g End Sect.

c. Gen. Tsunnion 4 C C - - C - - -- -

d. Gen. Outer 10.3 C C = - C -- - - -

shleid (Upper) i *

! e. Gen. Outer 10.8 C C ~ - C = - - -

shield (Imuer)

t. Gen. Inner 1 C C = - C - - - -

Shield

g. Gen. Tessinal 18.1 C C - - C = = -- -

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h. IIP Tusbine 72 C C = - C -- -- - --

outer shelt suppest

1. MP Turbine 64 C C ~ - C - - - --

Outer aihe11 (tmuer)

j. HP Turbine 64 C C = - C ~ - -- -

autor k, t.P Turbine 63 C C ~ -

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Enhaust Wood

!. LP Turbine 64 C C - - 'C Inner Casing *i t1

m. LP Tushine 144 C C - --

C -- -- -- --

A-motor O 1 tD t (pg

n. LP Turbine 149 C C - - C - -- -- -- o B-lictor 04 1

o. LP Turbine 153 C C ~ -

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os Caldeline 1 Guideline 2 Culdeline 3 Guldellne 1 Guideline 5 Culdeline 6 Guideline 7 steasuse ! Measuse 6 Capac8ty Sete Imad Csane oposatos special Lif tiseg Csame r Test Technical spec 8a!

Heavy leade _tional Pattie Psoceduses Tsaining Devices . slinee and Inapectlas Crane Geh specificationn attention a

s R p. LP Tusbane 6 C C - - C - - -- --

g Diagdesage

3. Deutsculatloa 25 -- - R - -

S - -- --

Pump Mi kolet

a. statos motos 7.63 C C = - C - - -- --

b. mtos 2 C C - --

C = - - --

messinge

c. Gen. potos '7.9 C C - -

C =* == = =

(b 3 d. Gen. Deasings 2 C C - - C - - - -

e. Pluid Dstve II.S C C - -

C - - - -

(Day) *

f. Pluid Drive 28 C C - --

C -- -, - --

twett

4. Pump Stsuctuse 35/12 -- -- R -- --

A C - --

Csane

a. up sw Pump 3.S C C -- -- C -

b. NP EW Pump 3.15 C C ~ -- C - - -. ==

Ntos

c. MP bW Pump 2 C C - - C = -- -- --

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d. knesgency bW 3.7% C C = - C == - --

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e. Emesgency SW  !.S C C -- --

C - - -- == 4 Pump netos w

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9, Isel@t latesin Interin g3 os Guideline I Guideline 2 Guide!!ae 3 Guideline 4

• Culdeline S Guideline 6 Guideline 7 Measure I seeamuse 6 Capacity safe load Crane opesetor special Eliting Crane - Test Technical Special usavy Imade Itonal Pathe Procedures Traintne Devices slines and Inesection Crane Desten specifications Attention

f. Fire Pump 1.15 C C ~ - C - - -- --

g a g. Fire Pump 8.6 C C - - C - -- - -

4 MMw ,

h. Fise Pump 1.6 C C = - C - - == =

Diesel Dsive

1. Cisc. teater 17 C C - - C - - - -

• Pump

j. Cisc. teater 18.8 C C - - C = - -- -

Pun *, postos

k. Sereice teater 7.6 C C - - C -- - -= =

g W 6 setot w

1 S. Sectaculation 24 - -- R - - R - - -

rump peotor Notet

s. Recirc. Pump 21.5 C C - - C - - - -

testor

b. pectac. Pump II.6 C C - - C - -- -- --

6. CBD Removal I C C R - - 3 - - .-

Platform Winch .

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7. CDD Demoval stoist 0.25 C C a - * - m - - -

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S. Equlgment Access 12 -- - R - -- a .. -- - gpg 1.ock seemoval O uolet

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Heavy Imada (tonal Pathe Procedures Trainine Devices $ lings and Inspection Crane Des h g lficatione Attention

a. Kloc. Imado 0.5 C C - - C - - - -

13. seesgency 0.5 - - R - - R - - --

t Cooling Tower P J1b Csone and

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a. Misc. Saada 0.5 C C = - C - - - -

14. CBD Transport 3 == = R - - R - -. .-

Jib Csene e

a. Misc. toada 3 C C = - C - - - -

15. CnD kanntenance 1 C C R - > - R - -

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TER-C550 6-379/380 2.1.1 Heavy Load Overhead Handling Systems

a. Summary of Licensee Statements and Conclusions n e Licensee has performed a detailed review and evaluation of load handling systems at Peacit Botton Units 2 and 3 and has datermined that the following load handling systems are within the scope of NUREG-0612: }

o reactor building crane o turbine building crane o recirculation pump motor / generator hoist o pump structure crane o recirculation pump motor hoist o control rod drive (CRD) removal platform winch hoist o CRD removal hoist o equipment access lock removal hoist o personnel lock hoist o torus equipment removal hoist o 15-ton yard crane o precoat material handling hoist (Unit 2 only) o emergency cooling tower jib crane and hoist o CRD transport jib crane o CRD maintenance jib crana.

The remaining load handling systems were eliminated from further consid-eration under NUREG-0612. 2ese load handling systems and the respective criteria by which they were excluded are as follows:

Criterion A Se crane or hoist is located in a structure which does not contain systems or equipment required for safe shutdown or decay heat' removal. Buildings and structures that do nct contain systems required for safe shutdown or decay heat removal are the administration building, screen structure, off-gas recombiner building, off-gas filter building, and off-gas stack. 2e following handling systems are located in these structures:

o machine shop crane o off-gas filter trolley o recombiner building hoist

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r TER-C5506-379/380 o off-gas stack hoist jib crane o screen structure trash handling equipment hoist.

Criterion B No equipment required for safe shutdown or decay heat removal is located in the load path for the crane or hoist. The load path is defined on tha load drawings. Equipment in the area was checked against

- revision 13 of the Q-list and the list of equipment required for safe shutdown contained in FSAR Supplement 2 to determine if the equipment is required for asfe shutdown or decay heat removal. The following handling l l

systems are in this category:

l o reactor feed pump crane o condensate pump hoist and auxiliary o Cad) transfer'/ removal winch o condensate domineralizer hoist and auxiliary o 5000-lb escapement door lif t hoist o 2500-lb escapement door lif t hoist o radwaste building hoist , ,,

o fuel pool filter domineralizer hoist ,- .

o circulating water pump structure trash handling equipment hoist o radwaste building equipment hoist o CRD jib crane j o CRD storage jib crane.

The table provided by the Licensee indicates that irradiated fuel and safety-related equipment at all plant elevations were considered in the evaluation.

In addition, the Licensee states that a mechanical stop that cannot be bypassed has been permanently added to the diesel generator rails, which will protect any safety-related equipment. The diesel generator cranes are only used when the respective diesel generator has been placed out of commission for maintenance or repairs.

b. Evaluation and Conclusion The Licensee's contention that NUREG-0612 is not applicable to those l handling systems identified is consistent with NUREG-0612.

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TER-C5506-379/380 2.1.2 Safe Load Paths' (Guideline 1, NUREG-0612, Section 5.1.l(1)]

" Safe load paths should be defined for the movement of heavy leads to minimize the potential for heavy loads, if dropped, to impact irradiated fuel in the reacter vessel and in the spent fuel pool, ce to impact safe shutdown equipment. The path should follow, to the extent practical, structural floor members, beams, etc., such that if the load is dropped, the structure is more likely to witnatand the impact. These load paths shculd be defined in procedures, shown on equipment layout drawings, and clearly marked on the floor in the area where the load is to be handled.

Deviations from defined load paths should require written alternative procedures approved by the plant safety review committee."

a. Summary of Licensee Statements and Conclusions The Licensee has provided drawings detailing the locations of safe load

paths, spent fuel, and safety-related equipment. Operation of the overhead handling systems in question is governed by one or more of the following procedures

M17.2 - Reactor Building Crane Operation MA7 - Procedure for Handling Q-Listed Items (Maintenance Division)

CD13.1 - Procedure for Handling Q Listed Items (Construction Division) .

The drawings provided by the Licensee define safe load paths for the movement of heavy loads that minimize the potential for heavy loads, if dropped, to impact irradiated fuel in the reactor vessel and in the spent fuel l pool, er to impact safe shutdown equipment. A draf t administrative procedure

. (Procedure for the Control of Heavy Loads) stipulates that cognizant supervisors shall " review safe load path drawings and determine if the proposed handling can be performed while avoiding exclusica zones." (An exclusion zone is defined as the area of the reactor vessel or spent fuel l

pool, or other areas where an accidental drop of the heavy load could damage irradiated fuel or a safe shutdown system without a redundant system.) The decision for the actual load path rests with the cognizant construction supervisor or maintenance supervisor. Since the draf t administrative procedure will be approved by the Plant Operations Review Committee, the authority of the cognizant supervisor in this matter has been vested by this I committee.

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TER-C550 6-379/380 The Licensee has taken exception to the requirement that safe load paths be marked on the floors. Load movement is directed by a signalman who is responsible for signaling and directing the crane operator along the designated load path specified in the Item Handling Report (IHR) .

b. Evaluation The safe load paths specified by the Licensee meet the intent of Section 5.1.l(1) of NUREG-0612. Since a cognizant supervisor designated by the Plant Operations Review Committee reviews the safe load paths and authorizes any deviations, the PECO approach to handling load path deviations at Peach Bottom Station is consistent with NUREG-0612. Further, the use of dedicated signalmen to' guide the crane operator along the load path is an acceptable alternative to load path markings.

c. Conclusion . . - -

The implementation of safe load paths at Peach Bottom Station Units 2 and 3 is consistent with Guideline 1 of NUREG-0612. )

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2.1.3 Load Handling Procedures (Guideline 2, NUREG-0612, Section 5.1.l(2)]

" Procedures should be developed to cover load handling operations for heavy loads that are or could be handled over or in proximity to irradiated fuel or safe shutdown equipment. At a minimum, procedures should cover handling of tnose loads listed in Table 3-1 of NUREG-0612.

These procedures should ir.cludes identification of required equipment; inspections and acceptancre criteria required before movement of load; the l steps and proper sequence to be followed in handling the load; defining l t

the safe path; and other special precautions."

I l a. Summary of Licensee Statements and Conclusions l The Licensee has stated that procedures governing the movement of heavy l loads handled by NUREG-0612 load handling systems includes A - Procedure for Control of Heavy Loads l

j M17.2 - Reactor Building Crane Operation i

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TER-C550 6-379/380 MA' - Procedurs for Handling Q-Listed Items (Maintenance Division)

CD13.1 - Procedure for Handling Q-Listed Items (Construction Division) .

Admir.istrative F'rocedure 'A' generically addresses load handling by those load handling systems subject to the general guidelines of NUREG-0612.

Procedures MA7 and CD13.1 provide specific details and methods of implemen-tation to be used by maintenance and construction divisions.

Procedures MA7 and CD13.1 classify handling activities into one of three categories based on ANSI N45.2.2-1972 (Packaging, Shipping, Receiving and Handling of Items for Nuclear Power Plants):

Category At Load requires specially selected equipment and detailed procedures for handling operations because of large size and weight.

Examples of items that may be assigned to this category ares o reactor vessels o steam generators i o major components of reactor vessel internals o spent fuel casks.

Catecory B: Load is handled with conventional handling equipment but requires detailed procedures because of weight, size, susceptibility to shock damage, high nil-ductility transition temperature, or any similiar conditions. Examples of items that may be assigned to this category ares o primary and intermediate coolant pumps and their internals o , safety-related instrument cabinets and control boards o control rod drive mechanisms l o fuel handling equipment o purification equipment o fuel o core components (small) o reactor vessel head.

Category C: Load is handled with conventional equipment using standard

! rigging practice. Construction and permanent plant materials not j included in Categories A or B are included in this category.

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When the cognizant suoervisor has determined that Achainistrative

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Procedure 'A' shall be invoked, an IHR shall be prepared which includes:

r o sketch of the proposed rigging arrangement l o size of the rigging tools to be used

'o specific lift points I

o center of gravity of the item o size, length, and angle of all chokers, slings, and chain hoists.

For Category 'A' items, separate detailed procedures will be prepared.

For Category 'B' items, special handling instructions will be specified with the IHR. -

I b. Evaluation.

The procedures referenced in, and provided with, the Licensee's response appear to provide the protection against load handling accidents y intended by Guideline 2 of NUREG-0612. Administrative Procedure 'A' provides the overall controls intended by Section 5.1.1(2) of NUREG-0612. Each lift requires a l

unique IHR with specific load handling instructions. The IHR is reviewed and l- approved by the cognizant supervisce authorized by the Plant Operations Review Committee. The specific division procedures provide additional details for the ,

handling of specific loads by classifying the loads into different categories.

l c. Conclusion The implementation of load handling procedures at Peach Botton Units 2 and 3 is consistent with Guideline 2 of NUREG-0612.

2.1.4 Crane Operator Training [ Guideline 3, NUREG-0612, Section 5.1.l(3)] )

" Crane operators should be trained, qualified and conduct themselvcs in accordance with Chapter 2-3 of ANSI B30.2-1976, ' Overhead and Gantry Cranes' [9]." l l

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. a. Summary of Licensee Statements and Conclusions s

The Licensee has stated that procedures MA20, CD2.1, and CD10.2 describe operator training, qualification, and conduct. Although no exceptions are taken to ANSI B30.2-1976, procedures do not presently invoke the standard.

Wowever, revisions have been initiated to rectify this matter. Steps have been taken to ansure that crane operators meet ANSI B30.2-1976 requirements. 1

b. Evaluathgn When revised, PECO's procedures for crane operator training, qualifi-cation, and conduct will satisfy Guideline 3 of NUREG-0612 on the basis of the Licensee's verification that the program will bc based on ANSI B30.2-1976.

However, it should be noted that MA20, CD2.1, and CD10.2 apply primarily to personnel indoctrination and rigger training. Consequently, significant revisions will be necessary to meet the ANSI R30.2-1976 training, qualifica-tion, and conduct requirements for crane operators.

c. Conclusion and Recommendations Crane operator training at Peach Botton Units 2 and 3 will be consistent with Guideline 3 when crane operator training, qualification, and conduct requirements are revised in accordance with the Licensee's commitments.

2.1.5 Special Lif ting Devices (Cuideline 4, NUREG-0612, Section 5.1.l(4))

"Special lif ting devices should satisfy the guidelines of ANSI N14.6-1978,

' Standard for Special Lifting Devices for Shipping Containers t ';hing i 10,000 Pounds (4500 kg) or More for Nuclear Materials' [10]. Tr.12 standard should apply to all special lifting devices which carry het loads in areas as defined above. For operating plants certain l.

inspections and load tests may be accepted in lieu of certain material requirements in the standard. In addition, the stress design factor stated in Section 3.2.1.1 of ANSI N14.6 should be based on the combined maximum static and dynamic loads that could be imparted on the handling device based on characteristics of the crane which will be used. This is in lieu of the guideline in Section 3.2.1.1 of ANSI N14.6 which bases the stress design factor on only the weight (static load) of the load and of the intervening components of tne special handling device."

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a. Summary of Licensee Statements and Conclusions .

The following special lifting devices are used at Peach Botton Units 2 and 3 to carry heavy loads over or in the vicinity of spent fuel or safety- l related equipment.

,o reactor pressure vessel (RPV)/drywell head strongback

! o fuel cask yoke ,

o hydraulic tensioner lifting device l

o dryer / separator sling (with hock box) o service platform sling j o Type 1 Iryer/ separator pool plug liftino device o fuel pcol gates lifting device.

Detailed arslyses have been performed for each of the above devices with l

the following recults [7].

l o RPV/drywell head strongbacks ' This device does not fully meet the guidelines of NUREG-0612 but can be modified to satisfy these guidelines.  ?

o Fuel cask yoke: The fuel cask yoke will be provided by the spent fuel

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cask supplier and will be evaluated for compliance with ANSI N14.6-1978 on a case-by-case basis.

o Hydraulic tensioner lifting devices The hydraulic tensioner lifting devices for both units meet the criteria of NUREG-0612. The tensioner lifting attachments for Unit 2, however, do not satisfy NUREG-0612 and should be replaced with the same type attachment uced at Unit 3.

o Dryer / separator sling: Certain components of this device do not satisfy NUREG-0612 criteria. They can, however, be modified to meet these criteria. l o Service platform slings: The lifting rings on the service platform do not satisfy this guideline. They may, however, be replaced with lugs 3

which will satisfy this guideline.

o Type 1 dryer / separator pool plug lifting device: This device is being modified and upgraded to comply with the guideline. This device will be designed to provide redundant load paths.

o Fuel pool ga'te lifting points: The cesign of these attachment points is consistent with this guideline.

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In Reference 8, PECO indicated its intent to complete the necessary modifications to the aforementioned lif ting devices prior to the end of 1983.

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Furthermore, PECO noted that speciai UftiiAUevicedill be subject to a continuing compliance testing program which meets the requirements of ANSI N14.6-1978 with the following exceptions / clarifications.

o Inspections will be performed once per reactor operating cycle rather than. annually.

J Critical welds will be condestructively examined in lieu of the assembly 150% load test.

b. Evaluation Design reviews performed by the Licensee indicate that the designs of several of the special lif ting devices satisfy the stress design factors of NUREG-0612 and ANSI N14.6-1978, including the followings . the RPV insulation removal lif ting device, the fuel pool gate lif ting device, and the Unit 3 hydraulic tensioner. Modification of remaining lifting devices in accordance j with vendor recommendations is in progress and, when complete, should satisfy ANSI design criteria for these lif ting devices. Proposed Licensee action regarding shipping cask yokes is consistent with the intent of this guideline.

c. Conclusion and Recommendations Special lifting devices employed at Peach Bottom Units 2 and 3 will provide a degree of load handling reliability consistent with that inherent in Guideline 4.

2.1.6 Lifting Levices (Not Specially Designed) (Guideline 5, NUREG-0612, Section 5.1.1(5)1

" Lifting devices that are not specially designed should be installed and

' used in accordance with the guidelines of ANSI B30.9-1971, ' Slings' j [11]. However, in selecting the proper sling, the load used should be the sum of the static and maximum dynamic load. The rating identified on the sling should be in terms of the ' static load' which produces the maximum static and dynamic load. Where this restricts slings to use on only certain cranes, the slings should be clearly marked as to the cranes with which they may be used."

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! a. Summary of Licensee Statements and Conclusions

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'l Peach Bottom procedures require that all slings used to lift equipment over or in the proximity of safety-related equipment meet the requirements of ANSI E30.9-1971. In addition, a dynamic load factor of 25% of dead load will be used in selecting these slings.

b. Evaluation and Conclusion i The selection and maintenance of slings at Peach Botton Units 2 and 3 is consistent with Guideline 5.

2.1.7 CraneskInspection, Testing, and Maintenance) {cuideline 6, NUREG-0612, Section 5.1.1(6)]

"The crane should be inspected, testtd, and maintained in accordance with

• Chapter 2-2 of ANSI B30.2-1976, ' Overhead and Gantry Cranes,' with the exception that tests and inspections should be performed prior to use

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l. where it is not practical to meet the frequencies of ANSI B3042 .for periodic inspection and test, or where frequency of' crane use fs less than the specified inspection and test frequency (e.g., the polar crane inside a PWR containment may only be used every 12 to 18 months during

. refueling operations, and is generally not accessible during power operation. ANSI B30.2, however, calls for certain inspections to be performed daily or monthly. For such cranes having limited usage, the inspections, test, and maintenance should be performed prior to their use)."

a. Summary of Licensee Statements and Conclusions The Licensee has stated that current maintenance procedures covering crane l

l inspection, testing, and maintenance are based on ANSI B30.2-1967, which PECO believes to satisfy the NBC's requirements for equivalence to ANSI B30.2-1976.

b. Evaluation The Licensee's evaluation of crane inspection, testing, and maintenance at Peach Botton Units 2 and 3 is generally consistent with the requirements of this guideline. Only one significant change was noted which should be incor-potated into the present crane inspection program Paragraph 2-2.3.3,

• Adjust-ments and Repairs, item d, requires that "if repairs of load sustaining'

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. members are made by welding, identification of materials shall be made and appropriate welding procedures shall be followed."

Other changes to Section 2-2 in the 1976 version do not directly affect the load handling reliability of the handling system. In fact, in several cases, the 1976 version inspection requirements are less restrictive than those required by ANSI B30.2-1967.

c. Conclusion i

Inspection, testing, and maintenance of cranes at Peach Bottom Units 2 and 3 will provide a degree of load handling reliability consistent with Guideline 6,.

2.1.8 Crane Design (Guideline 7, NUREG-0612, Section 5.1'.l'(7)] '

"Thecraneshouldbedesihedtomeettheapplicablecriteriaand

! guidelines of Chapter 2-1 of ANSI B30.2-1976, ' Overhead and Gantry Cranes,' and of CHAA-70, ' Specifications for Electric overhead Traveling Cranes' [12] . An alternative to a specification'in ANSI B30.2 or CMhA-70 may be accepted in lieu of specific compliance if the intent of the specification is satisfied."

a. Summary of Licensee Statements and Conclusions The Licenses has stated that the pr~ocurement specifications for the reactor building cranes, turbine building cranes, and the pump structure crane stipulate compliance with the requirements of EOCI-61 [13] . At the time of i

manufacture of the above cranes, EOCI-61 was the accepted standard for crane design.

The Licensee has also completed an evaluation of those provisions of current standards (i.e., CMhA-70) which affect load handling reliability and appear more stringent than the standard imposed at the time of manufacture.

In the course of this review, the only exception to the current standard identified was the fact that the AGMA durability horsepower rating for the turbine building crane main hoist extra reduction gearing was approximately Since the strength horsepower rating

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I 34% less than that required by CMAA-70.

exceeds that' required by CMAA ho and it is known that durability horsepower is

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associated with prevention of local failures (e.g., pitting), it was proposed that this discrepancy was of minimal significance with respect to crane reliability. Furthermore, the Licensee indicated that compensation for this

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deviation will be provided by the addition of a maintenance procedure to check the backlash and surft.:e pitting of the extra reduction gearing of each crane durik its scheduled inspection.

Since CMAA-70 and B30.2-1376 apply to top-running overhead bridge and gantry cranes, the balance of the cranes listed in Section 2.1.1 of this report are not covered by these specifications. The miscellaneous cranes and hoists purchased for Pea'ch Bottce Units 2 and 3 were industry standard hoists and .

monorails requfred to comply with portions of EOCI-61.

b. Evaluation' '

An independent review of the crane design data provided in References 5, 7, and 8 indicates that the reactor building, turbine hall, and pump , structure ,

cranes meet the intent of Section 5.1.1(7) of NUREG-0612.

It is agreed that the deviation noted with respect to the durability horsepower rating of the turbine building crane main hoist is not a significant issue with respect to a potential load drop and can be appropriately compen-sated by the proposed inspection program.

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c. Conclusion and Recommendations 1

[ The design of overhead electric travelling cranes handling loads subject

- to NUREG-0612 at Peacn Bottos Units 2 and 3 provides a degree of load handling l reliability consistent with the requirements of Guideline 7.

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1.2 INTERIM PROTECTION MEASURES The NBC has established six interim protection measures to be implemented

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. at operating nuclear power plants to provide reasonable assurance that no heavy loads will be handled over the spent fuel' pool and that measures exist to reduce the potential for accidental load drops to impact on fuel in the core or spent fuel pool.- Four of. the six interim measures of the report consist of

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s TER-C5506-379/380 Guideline 1, Safe Load Paths; Guideline 2, Load Handling Procedures; Guideline 3, Crane Operator, Training; and Guideline 6, Cranes (Inspection, Testing, and Maintenance). The two remaining interim measures encompass the following criteria:

1, Heavy load technical specifications

2. Special review for heavy loads hanriled over the core.

The Licensee's implementation of these interim protection measures is summarized and evaluated in the succeeding paragraphs of this section.

2.2.1 Technical Specifications (Interim Protection Measure 1, NUREG-0612, Section 5.3 (1} }

" Licenses for all operating reactors not having a single-failure-proof overhead crana in the fuel storage pool area should be revised to include a specification comparable to Standard Technical Specification 3.9.7,

' Crane Travel - Spent Fuel Storage Pool Building,' for PWR's and Standard .

Technical Specification 3.9.6.2, ' Crane Travel,' for BWR's, to prohibit handling of heavy loads over fuel in the storage pool until implementa-tion of measures which satisfy the guidelines of Section 5.1."

a. Evaluation Although the Licensee did not make a specific statement regarding Interim Protection Measure 1, Special Precaution 2 of Procedure M17.2 (Reactor Building Crane Operation) states the following:

" Loads of 1000 lbs or greater shall not be moved over fuel assemblies in the fuel pool at any time, per Tech. Spec. 3.10.D.'

b. Conclusion Peach Botton Units 2 and 3 comply with Interim Protection Measure 1 based on the limitations contained in Technical Specification 3.10.D.

2.2.2 Administrative Controls (Interim Protection Measures 2, 3, 4, and 5, ,

NUREG-0612, Sections 5.3 (2)-5.3 (5))

" Procedural or administrative measures [ including safe load paths, load handling procedures, crane operator training, and crane inspection] . .. '

can be accomplished in a short time period and need not be delayed for ,

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TER-C5506-379/380 l completion of evaluations and modifications to satisfy the guidelines of Section 5.1 of [NUREG-0612] ."

a. Summary of Licensee Statements and Conclusions _

Summaries of the Licensee's statements and conclusions are contained in discussions of the respective general guidelines in Sections 2.1.2, 2.1.3, 2.1.4, and 2.1.7.

l Evaluations, Conclusions, and Recommendations  !

b.

I The evaluations, conclusions, and recommendationa are contained in  ;

discussions of" the respective general guidelines in Sections 2.1.2, 2.1.3,  !

i 2.1.4, and 2'.1.7.

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'2.2.3 Special Reviews for Heavy Loads Over the Core (Interim Protection Measure 6, NUREG-0612, Section 5.3 (1)1 ,

"Special attention should be given to procedures, equipment, and ,

personnel for the handling of heavy loads over the core, such as vessel l internals or vessel inspection tools. This special review should include 1 the following for these loads: (1) review of procedures for installation of rigging or lifting devices and movement of the load to assure that  ;

sufficient detail is provided and that instructions are clear and concise; (2) visual inspections of load bearing components of cranes, l slings, and special lif ting devices to identify flaws or deficiencies that could lead to failure of the component; (3) appropriate repair and replacement of defective components; and (4) verify that the crane l

operators have been properly trained and are familiar with specific t procedures used in handling these loads, e.g., hand signals,' conduct of operations, and content of procedures.' I

a. Suasary of Licensee Statements and Conclusions The Licensee has stated that the reviews recommended by Interim j Protection Measure 6 were completed prior to May 15, 1981. j l

b. Evaluatior$, Conclusion, and Recommendations Peach Botton Units 2 and 3 comply with Interim Protection Measure 6.

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3. CONCLUSION This summary is provided to consolidate the results of the evaluation contained in Section 2 concerning individual NRC staff guidelines into an i

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overall evaluation of heavy load handling at Peach Bottom Units 2 and 3.

Overall conclusions and recommended Licensee actions, where appropriate, are provided with respect to both general provisions for load handling (NUREG-0612, Section 5.1.1) and completion of the staff recommendations for interim protection (HUREG-0612, Section 5.3).

I 3.1 GENERAL PROVISIONS FOR LOAD HANDLING The NBC staff has established seven guidelines concerning provisions for handling heavy loads in the area of the reactor vessel, near stored spent fuel, or in other areas where an accidental load drop could damage equipment required for safe shutdown or decay heat removal. The intent of these guidelines is twofold. A plant conforming to these guidelines will have developed and implemented, through procedures and operator training, safe load travel paths such that, to the , maximum extent practical, heavy loads are not carried over or near irradiated fuel or safe shutdown equipment. A plant conforming to these guidelines will also have provided sufficient operator -

training, handling system design, load handling instructions, and equipment l inspection- to ensure reliable operation of the handling system. As detailed i

in Section 2, it has been found that load handling operations at Peach Bottem Units 2 and 3 can be expected to be conducted in a highly reliable manner consistent with the staff's objectives as expressed in these guidelines, 3.2 INTERIM PROTECTION MEASURES The NBC staff has established in NUREG-0612, Section 5.3, certain measures that should be initiated to provide reasonable assurance that handling of heavy loads will be performed in a safe manner until final implementation of the general guidelines o'f NUREG-0612, Section 5.1 is complete. Specified measures include the implementation of a technical specification to prohibit the handling of heavy loads over fuel in the storage pool; compliance with l

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Guidelines 1, 2, 3, and 6 of NUREG-0612, Section 5.1.1; a review of load handling procedures and operator training; and a visual inspection program, including component repair or replacement, as necessary, of cranes, slings, and special lifting devices to eliminate deficiencies that could lead to component failure. Peach Botton Units 2 and 3 have satisfactorily completed the interim protection measures.

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4. REFEPENCES

1. " Control of Heavy Loads at Nuclear Power Plants" NBC, July 1980 NUREG-0612

2. V. Stello, Jr. (NRC)

Letter to all Licensees

Subject:

Request fer Additional Information on, Control of Heavy Loads Near Spent Fuel May 17,19'/8

3. NBC

. Letter to Philadelphia Electric Company.

Subject:

NBC Request for Additional Information on Control of Heavy Loads Near Spent Fuel December 22, 1980

4. S. L. Daltroff (PECO)

Letter to D. G. Eisenhut (NRC)

Subject:

Control of Heavy Loads at Peach Boctom Atomic Power Station June 18, 1981

5. S. L. Daltroff (PECO)

Letter to D. G. Eisenhut (NRC)

Subject:

Control of Heavy,Ioads at Peach Bcttom Atomic Power Station December 22, 1981'

6. S. L. Daltroff (PECO)

Letter to J. F. Stolz (NRC)

Subject:

Control of Heavy Loads May 20,1982

7. S. L. Daltroff (PECO)

Letter to J. F. Stolz (NRC)

Subject:

Control of Heavy Loads October 25, 1982

8. S. L. Daltroff (PECO)

Letter to J. F. Stol: (NBC)

Subject:

PBAPS NUREG-0612 August 10, 1983

9. " Overhead and Gantry Cranes" New York: American National Standards Institute, 1976 ANSI B30.2-1976 10 . " Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500 kg) or More for Nuclear Materials" American National Standards Institute ranklin Resear

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11.

' Flings' American National Standards Institute

1. ANSI B30.9-1971 i

12 . " Specifications for Electric Overhead Traveling Cranes" l

, Pittsburgh, PA: Crane Manufacturers Association of America, 1975 l

CMAA-/0 -

. I J 13 . " Specifications.for' Electric Overhead Traveling Cranes" 'T Pittsburgh, PA: Electric Overhead Crane Institute,1961 EOCI-61 I. .-

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