ML20136B916

Summary of 851031 Meeting W/Util & B&W in Bethesda,Md Re Requested Exemption from GDC 4 Requirements for Reactor Coolant Pump Supports.Viewgraphs Encl

ML20136B916
Person / Time
Site:	Crystal River
Issue date:	11/13/1985
From:	Silver H Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8511200322
Download: ML20136B916 (27)

Text

f.

'Nav ber 13,1985 .

f Docket No~ .- 50-302

' LICENSEE:~ . Florida Power Corporation FACILITY: Crystal River Unit No. 3

SUBJECT:

1 SUM 4ARY OF MEETING TO DISCUSS REQUEST FOR EXEMPTION FROM GDC-4 REQUIREMENTS Introduction The NRC staff met in Bethesda, Maryland with representatives of Florida Power l Corporation (FPC, the licensee) and Babcock & Wilcox (B&W) on October 31, 1985 to discuss the licensee's requested exemption from GDC-4 requirements for reactor coolant _ pump.(RCP) supports. Representatives of A/E's and other vendors ~and licensees were also present. The list of participants is included as Enclosure 1.

Discussion The principal purpose of the meeting, requested by the licensee, was to summarize FPC positions on technical aspects of reducing the number and size of.RCP snubbers, to address items of concern previously raised by the NRC staff,'and to identify additional staff questions based on its review to

'date. The licensees presentation covering the first two items is outlined in Enclosure'2. . Significant matters of discussion and additional staff concerns are sumarized below.

It was noted that the schedule for promulgation of the final rule could

. result in publication in the Federal Register in January _1986. If the rule as published covers the licensee's proposed change, an exemption would not be required. FPC noted that since it needs early NRC action, it can only proceed with a request for' exemption from the present rule. In any event, the staff's technical . review would be essentially the same for an exemption

> as for verification of conformance to the revised rule.

In discussing FPC's analysis, it was pointed out that the system dynamic

- analysis had been completely redone to reflect all remaining loads after removal of LOCA loads. Stress margins summarized on page 20 of Enclosure 2 are relative to USAS B31.7-allowable stresses and result from pressure,

~

= deadweight, and OBE loads, the governing load combination. NRC noted that

, similar information should be provided on component nozzles, and inquired as to why SSE loads were not governing. Also, NRC indicated that FPC should

. verify whether there are any hydraulic transients which should also be

. included in the analysis. -The question of benchmarking of two codes used in 4the analysis was raised. FPC noted that the codes had been qualified to B&W requirements and audited by the NRC, but agreed that this had not been documented. FPC was requested to provide this documentation. To clarify the

$bbbha PDR

m factors of safety resulting from the new analysis presented on page 7 of Enclosure 2, it .was explained that these were the factors by which loads would have to increase to cause yielding of the snubbers and resultant yielding of the component supports. The NRC staff requested that a comparison be provided of new margins based on the FSAR allowable stresses.

A useful discussion took place of the reliability of the new snubber system compared with the present system (pps 18 and 19, Enclosure 2). The NRC staff requested that the reliability discussion be documented and formally docketed.

The NRC staff suggested that the licensee consider independent verification of.the revised design and installation. The design verification need not include a separate. analysis, but should include a technical assessment of the process, inputs, and interfaces.

The staff review of the generic B&W analyses (BAW-1847 Rev. 1) is almost complete and all technical problems are expected to be resolved by the end of

. November.

Since the licensee submittal on leak detection capability had been received by the staff only the day before the meeting, only a cursory review had been performed. Based on that review, no comments or questions were raised. With regard to the value-impact analysis, a breakdown of the total man-hours for snubber maintenance was requested.

The-licensee indicated that it would respond to the above requests and comments as soon as possible, and reiterated its desire for preliminary indication of acceptability of its exemption request by the end of November to permit initiation of procurement actions.

criglal temd M Harley Silver, Project Manager Operating Reactors Branch #4 Division of Licensing W

HSilver;cr RBo ak g,6erup 11/f*J85 11/ 85 p j3-f[

Enclosure 1 OCTOBER 31, 1985 MEETING ON GDC-4 EXEMPTION Attendees Affiliation Brenda Mozafari NRR - Project Manager Randy Schaefer Babcock & Wilcox Joe, R. Maseda FPC - Engineering Mark Hartzman NRC/NRR/DE/MEB

- '~

. Bob Bosnak NRC/DE R. W. Klecker _ NRC/MTEB John O'Brien NRC/DET/RES Bill Shields NRC/ ELD Larry Tittle FPC - Engineering C. L. Buty Bechtel Mike Lamastra NRR/DSI/RAB Keshab K. Dwivedy Virginia Power - Eng.

Melvin S. Whitt Virginia Power - Eng.

George H. East Stone & Webster - EMD Joe Hegner Virginia Power - Lic.

Richard K. MacManus Virginia Power - Eng.

Harry Clark Westinghouse H. L. Bramer NRC/DE/MEB

- Harley Silver NRC/DL Frank Cherny NRC/MEB/NRR Ken Wilson ,

Florida Power Corp.

Licensing Keith Wichman NRC/MTEB E. H. Davidson Florida Power Corp.

Licensing

--- - _ _ _ _ _ _ _ _ -_ __ ____ - ~ " ~ - - __,__

Enclosure 2 PRESENTATION BY FLORIDA POWER CORPORATION (FPC)  :

55COND PEEETING BETWEEN NRC/FPC TO DISCUSS PARTIAL EXEMPTION FROM GDC 4 L

Bethesda, Md.

Room P-422 Phillips Building l

October 31,1985

. I

~

AGENDA 1:00 P.M. I. INTRODUCTORY REMARKS H. Silver, NRC IDENTIFICATION OF ATTENDEES

~ E. H. Davidson, FPC

- ' ~605 P.M. II. PURPOSES OF MEETINGS 1:10 P.M. IU. REVIEW OF PREVIOUS DOCUMENTATION E. H. Davidson, FPC TO NRC 1:20 P.M. IV.

SUMMARY

OF TECHNICAL ISSUES IDENTIFIED BY NRC; STATUS OF 3. R. Maseda, FPC RESOLUTION BY FPC R. Schaefer, B&W 2:00 P.M. V. IDENTIFICATION OF ADDITIONAL TECHNICAL INFORMATION NEEDE1.1 NRC Representatives BY NRC K. R. Wilson, FPC VI.

SUMMARY

NEXT STEPS NEEDED 2

15 P.M.

2:30 P.M. VII. ADJOURN 1

O IL PURPOSES OF MEETINGS FIRST MEETING - LARGELY ADMINISTRATIVE; IDENTIFIED PLANNING, (Aug. 5,1985) DOCUMENTATION, AND SCHEDULING

'". ' ~ his MEETING - PRIMARILY TECHNICAL; IDENTIFY POSITIONS OF FPC AND REMAINING QUESTIONS BY NRC OVERALL - 1) OBTAIN INFORMAL RULING BY NRC DURING NOVEMBER 1985 TO PERMIT FPC PROCUREMENT ACTIONS

2) OBTAIN NRC PARTIAL EXZMPTION FROM GDC-4 ,

DURING FEBRUARY 1986 l

2

III. REVIEW OF PREVIOUS DOCUMENTATION TO NRC DOCUMENT DATE

_. .-- A. B&W GENERIC SUBMITTAL OCT. 7,1984 BAW-1847 B. EPC LET-TER TO NRC REQUESTING PARTIAL FEB.1,1985 EXEMPTION FROM GDC-4 C. CRYSTAL RIVER 3 LBB EVALUATION OF AUG. 30,1985 RCS PIPING LOADS D. CRYSTAL RIVER 3 SAFETY BALANCE /VALUE SEPT. 27,1985 IMPACT STATEMENT E. B&W GENERIC SUBMITTAL OCT. 7,1985 BAW-1847, REV.1 F. RCS LEAKAGE DETECTION SYSTEM OCT. 29,1985 7

CAPABILITY EVALUATION NOTE: REPORTS A AND E SPONSORED BY B&W OWNERS GROUP l l l

l 3

l

4 III A. PRINCIPAL CONCLUSIONS OF BAW-1847 DOUBLE ENDED GUILLOTINE BREAK OF GDC 4 IMPLAUSIBLE.

DETECTABLE LEAK RATES RESULT IN NO FLAW

- GROWTH OR STABLE FLAW GROWTH.

POSTULATED LEAKAGE FLAW SIZES ARE MUCH SMALLER THAN CRITICAL FLAW SIZE WHICH MIGHT LEAD TO PIPE FAILURE.

CONTROLLED REACTOR SHUTDOWN CAN OCCUR BEFORE PIPE WOULD FAIL IN A CATASTROPHIC PANNER.

i

[

t i

l_

• e

(

III B. ' FPC LETTER TO NRC OF PEB.1,1985 SCOPE OF REOUEST:

APPROVAL OF THIS EXEMPTION WILL ALLOW FPC TO REDESIGN

, _ THE RCS PUMP RESTRAINT SYSTEM IN ORDER TO:

~

o REMOVE SEVERAL LARGE BORE HYDRAULIC SNUBBERS CURRENTLY RESTRAINING THE REACTOR COOLANT

~ PUMPS ((JP TO 20 OUT OF A TOTAL OF 32).

o REPLACE OTHER REACTOR COOLANT PUMP LARGE BORE SNUBBERS WITH RIGID RESTRAINTS (4 RESTRAINTS).

j o REPLACE REMAINING REACTOR COOLANT PUMP LARGE BORE SNUBBERS WITH SMALLER SNUBBERS (8 SMALLER SNUBBERS).

GRANTING REOUEST WOULD NOT AFFECT:

o ECCS DESIGN BASIS.

o REACTOR BUILDING AND COMPARTMENT DESIGN BASIS.

o EQUIPMENT QUALIFICATION BASIS.

o ENGINEERED SAFETY FEATURE SYSTEMS RESPONSE.

~

o CURRENTLY INSTALLED P!PE WHIP RESTRAINTS, JET IMPINGEMENT SHIELDS AND SMALL BORE RCS SNUBBERS.

I l

._ . ~~ _ III C. LBB EVALUATION OF RCS PIPING LOADS o

NEW SUPPORT CONFIGURATION LOADINGS ARE ENVELOPED BY THE GENERIC ANALYSIS (WITH A MARGIN OF 6.6% AT THE MAXIMUM LOAD LOCATION).

o NEW FACTORS OF SAFETY FOR CR-3 COMPONENT SUPPORTS ARE SUFFICIENT.

6

III C. (CONT'D)

, , FACTORS OF SAFETY FOR CR-31 REACTOR PRESSURE VESSEL 12.7 STEAM GENERATOR 34.2 REACTOR COOLANT PUMP 4.6 I

CALCULATED METHODOLOGY BY B&W IN A MANNER SIMILAR TO LLNL Wh i

7

III D. . SAFETY BALANCE /VALUE IMPACT STATEMENT o

ANALYSES (BY BatW) USED METHODS OF LLNL o

- , i. SAFETY BALANCE IS MAN-REM EXPOSURE INCREASE TO PU MAN-REM' EXPOSURE DECREASE TO CR-3 WORKERS o

INCREASE IN RISK TO PUBLIC ASSUMED RELATED TO REMOV h

PROTECTION FROM DYNAMIC EFFECTS OF RCS PRIMARY P o

DECREASE IN RISK TO WORKERS ASSUMED FROM DECISI PROTECTION AND LESSEN PERIODIC IN-SERVICE INSPEC -

o VALUE-IMPACT

SUMMARY

FOR CR-3 BASED ON REMAINING YEARS - NO OPERATING LIFE EXTENSION ASSUMED O

l' L

5 3

III D. (CONT'D)

SAFETY BALANCE VALUE SUMM ARY BEST HIGH LOW VALUE (M AN-REM) ESTIMATE ESTIMATE ESTIMATE

~,

PUBLIC HEALTH - -2.2E-6 -I.4E-1 0.0 OCCUPATIONAL EXPOSURE -1.7E-5 -7.8E-2 0.0 (ACCIDENTAL) - -

OCCUPATIONS EXPOSURE (ROUTINE) a) INSERVICE INSPECTION 30 75 3 b) ROUTINE MAINTENANCE 4 7 2 c) SPECIAL MAINTENANCE 7 14 1 d) REMOVAL OF NON-ISI P!PE WHIP RESTRAINTS -30 -125 -5 e) PUMP SNUBBER MAINTENANCE 2340 2340 2340 TOTAL QUANTIFIED VALUE 2331 2311 2341 POSITIVE VALUES = EXPOSURE DECREASE; NEGATIVE VALUES = EXPOSURE INCREASE CONCLUSION: BENEFITS FAR EXCEED RISK i

l l

4 III E. B&W GENERIC SUBMITTAL, BAW-1847, REV.1 o SUPERCEDES BAW-1847, BUT DOES NOT ALTER THE CONCLUSIONS

~~~ ~

~

o ADDRESSES COMMENTS OF NRC STAFF ARISING FROM REVIEW OF BAW-1847 o

NEW MATERIALS DATA USED IN ANALYSIS o

SUPPORTS APPLICATION OF LBB CONCEPT TO CR-3 AND OTHER PARTICIPATING BWOG UTILITY PLANTS o

NRC REVIEW COMPLETION REQUESTED (IN TRANSMITTAL LETTER) BY OCTOBER 31,1985

_ _ . _ . _ _ _ __ , , , , -g-----w*e

i

.i III F.

RCS LEAKAGE DETECTION SYSTEM CAPABILITY EVALUATION o

LEAKAGE DETECTION CAPABILITY AT CR-3 IS CONSISTENT WITH REG. GUIDE 1.45 11 - -

IV.

SUMMARY

OF TECHNICAL ISSUES IDEN trIcD BY NRC:

STATUS OF RESOLUTION BY FPC

- ~ ~~

Slides A.

IDENTIFICATION OF RC PUMP SUPPORT CONFIGURATION 13-17 B.

RELIABILITY OF NEW CONFIGURATION 18-21 C.

BENCHMARKING OF CODES -

l i

t l

12

r

~

_ _ RC PUMP SUPPORT CONFIGURATION PRESENT OPTIMIZF,Q QUANTITY 32 SNUBBERS (8/ PUMP) 8 SNUBBERS E-2/ PUMP) 4 RIGID STRUTS f"1/ PUMP)

SIZE 18" TO 25" BORE MAX. 14" BORE CAPACITY 1000 KIP TO 2000 KIP 400 KIP MASEDA(OH#.)ND75-3 .. .i

.s - L RCF.S-6A,bg $ RCF.S 7A

\

/i -

2..

~

/

L RC.95-BA 4

RC PUFJ 1A

, OF.5-1A RCF.5- 5.

RCP.S-4A RCF.S-2A RCF.5-3A 9

s/

,K, SNuss:R :.:y.:NA T LB SNuss R a:7:.AC=

3Y R:":D STRC l SNU33IF. 3"%'S Z :

F i

RCHS- 73 L

8 RCES-8B .

RCHS-63 .._

~~~

l RC PUMP RCES-53 13 t

ROES-u3 RCHS-13 1

ROES-33 RCES-23

}

\ /

-y SNU23IR I'.IMINA~ID

<~

-- gg Sh"J33IR RI?IAC 3 3Y RIG:D S RUT SN"33IR 00*aTS IO

r RCHS-1C i

' i

-- RCHS-8 RCHS-2C CMS-7C RC PUMP '

IC

'l f

yNs-SC 1

RCHS-5C g 8  !

RCHS-uc RCHS-30 1

/

J. .

\ /

_/ XT SNU33IR I,,:MINA-';;

M

~

3r a =C S R=

SNU23IR OCWS:;;;

^+

h /

RCHS-1D RCHS-BD RCHS-7D

/ s L

RCHS-2D RCHS-3D RC

's- PUH?

1D RCH5-c3 8

l

=,

RCHS-5D Rcns_sp B - ,s t- y W

G

[ g SNU33IR I.IM NA ID

' \

=

L8 ,. SNU33IR RI?*,ACI:

EY R:::: E R';-

[ ] SN"IIII 20W:I;--,

OPTIMIZED COMPONENT RELIABILITY

. -.__. SNUBBERS

. INTEGRAL RESERVOIR-PRESSURIZED MORE RADIATION RESISTANT FLUIO LONGER SEAL SERVICE LIFE IMPROVED CONTROL VALVE PERFORMANCElRELIABILITY TEST-IN-PLACE CAPABILITY LINK BARS-(STRUTS)

ONE-TIME INSTALLATION ONLY REQUIRES VISUAL INSPECTION l l

LARGE COMPONENT SUPPORTS ' '

ACCEPTABLE RV. OTSG SUPPORT MARGINS l

',t u a ' . . -* _ -- 1.C

e SYSTEM RELIABILITY OVERALL FLEXIBILITY OF PIPING SYSTEM INCREASED.

LOWER STRESS DURING THERMAL EXPANSION OF SYSTEM (HEAT-UPI COOL-DOWN). .

HIGHER SEISMIC STRESS (LOW PROBABILITY OF OCCURRENCE).

SUFFICIENT DESIGN MARGINS RETAINED FOR PIPING AND LARGE COMPO-NENT SUPPORTS.

MAsE C A( OH#3)NC75-3 ic I

l RCS PRIMARY PIPING DESIGN PRIMARY STRESS MARGINS I 1

l

- l New Succort Confiouration Old Sueoort Confiouration HOT LEG RV ,0utl e t 53%

60%

~

dTSG Inlet 61% 56%

~ ~

Minimum Margin 34% 24%

'UPoER COLD LEG - '

-RV Inle: 51% 49%

Pump Discharge 59% 57%

.Miritmum ML ,im 25% 25%

LOWER COLD LEG OTSG Outlet 41% 34%

Pumo Intake 57% 54%

Minimum Margin 3% 0%

l l

t l

20

e-CRYSTAL RlVER VERSUS GENERIC EVALUATION:

PicE SIZE GENERIC MAXIMUM MOMENT F3C MAXIMUM MOMENT

( Fi-KIPS - ) ( Fi- KIPS )

28" 1.D.

3in.NGHT 3098.0 AT Jt.12 2004.4 AT Jt. 21.5 -

A A0W 2822.8 AT Jt. 24 1617.0 AT Jt.-27.5

~b"1.D.

3

~ ~

daKAIGHT 2375.5 AT Jt. 9 2230.1 AT Jt. 9 m 40W -

2375.5 AT Jt. 9 2230.1 AT Jt. 9 21:3 5 --

GEN ".JC MNIMUM MOMENT 230 MNJMUM MOMENT

( Fi-KlPS ) ( :T-WJos )

28" LD. _

dadAlGHT 560 AT Jt.12 1555.1 AT Jt. 21.5 m AOW 1245 AT Jt. 24 1294.3 AT Jt. 27.5 36" l.D.

6: M.NGHT 1010 AT Jt. 9 1738.0 AT Jt. 9 m AOW 1010 AT Jt. 9 173E.0 AT Jt. 9

0

\

\

e av V. IDENTIPTCATION OF ADDITIONAL TECHNICAL INFORMATION NEEDED BY N 6

e *

(TO BE SUPPLIED BY NRC REPRESENTATIVES) 4 4

l

, 22

8' VL

SUMMARY

NEXT STEPS NEEDED l.

ADDITIONAL INFORMATION IDENTIFIED IN AGENDA ITEM V WILL BE ADDRESSED BY FPC 2.

NRC FORMAL RESPONSE TO FPC LETTER OF FEB.1,1985 (REQUESTING PARTIAL EXEMPTION FROM GDC 4) NEEDED DURING FEBRUARY 1986.

3.

NRC INFORMAL RESPONSE NEEDED QUICKLY (DURING NOVEMBER,1985) TO PERMIT INITIATION OF PROCUREMENT ACTIONS BY FPC 6

9

_ _ _ , . , ___ , - - , . - - - - - - - , - -nw-r' " " *' ' ' ' ' ' ~ ' ' " ' ' ' ~ ' ~ ' ~ ' ~" "

s MEETING StM4ARY DISTRIBUTION Licensee: Florida Power Corporation

• Copies also sent to those people on service (cc) list for subject plant (s).

Docket File NRC PDR L PDR ORBf4 Rdg Project Manager - H. Silver JStolz BGrimes (Emerg, Preparedness only)

OELD.

EJordan, IE ACRS-10 NRC Meeting

Participants:

BMozafari MHartzman BBosnak RKlecker J0'Brien BShields MLamastra HBrammer FCherny KWichman

. .