ML18018A754

Forwards Response to Request for Addl Info Re Draft SER Open Items Re Reactor Cavity & Electrical Separation Criteria Used in Cable Spreading Area

ML18018A754
Person / Time
Site:	Harris
Issue date:	09/19/1983
From:	Mcduffie M CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
LAP-83-419, NUDOCS 8309230411
Download: ML18018A754 (19)

Text

re REGULATORY FORMATION DISTRIBUTION SY M (RIOS)

ACCESSION NBR:8309230411

. DOC.DATE'3/09/19 NOTARIZED!

NO FAC'lL:50 400 Shearon Har r js Nuclear Power Pl anti Unit ii Car ol jna 50-401 Shearon Harris Nucl-ear Power Pl anti Unit ?i Carolina AUTH BYNAME AUTHOR AFF ILIAT'ION MCDUFFIEPM.A.

Carolina Power L Light Co.

REC IP ~ NAME RECIPIENT AFFILIATION DENTONiH ~ RE Office of Nuclear Reactor Regulationi Director DOCKET 0

05000400 05000401

SUBJECT:

Forwards response to rez0est for.addi info re draft SKR open items.re,reactor cavitv 8 electrical separation cniteria used in cable spreading area.

OISTRISUTION CODE:

SOOIS COPIES RECEIVED:LTR 'NCL SIZET TITLE: Llcenslno Surrmittel:

PSAR/PSAR Amdts I Related Correspondence NOTES:

REC IP lENT ID GOOF/NAME NRR/OL/ADL NRR L'B3 LA INTERNAL: 'ELD/HDS1 IE/DEPER/EPB 36 IE/OEQA/QAB 21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/OE/MEB 18 NRR/DE/SAB

?4 NRR/OHFS/HFEB40 NRR/DHFS/PSRB

'NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DSI/RSB 23 RGNR EXTERNALs ACRS 41 DMB/OSS (AMDTS)

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Carolina Power & Light Company SERIAL:

LAP-83-419 SEP 19 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS.

1 AND 2 DOCKET NOS. 50-400 AND 50-401 RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION

Dear Mr. Denton:

Carolina Power

& Light Company hereby transmits one original and forty copies of additional information requested by the NRC as part of the safety review of the Shearon Harris Nuclear Power Plant.

Some of the enclosed responses relate to Draft Safety Evaluation Report open items, while others relate to new issues.

The cover sheet of the attachment summarizes the related Open Item or the new issue addressed in the attachment along with the corresponding review branch and reviewer for each response.

We will be providing responses to other requests for additional information shortly.

Yours very truly, M. A. McDuffie Senior Vice President Nuclear Generation FXT/lcv (7860FXT)

Enclosure Mr. Wells Eddleman Dr. Phyllis Lotchin Mr. John D. Runkle Dr. Richard D. Wilson-Mr. G. 0. Bright (ASLB)

Dr. J.

H. Carpenter (ASLB)

Mr. J. L. Kelley (ASLB) cc:

Mr. B. C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Mr. J.

P. O'Reilly (NRC-RII)

Mr. Travis Payne (KUDZU)

Mr. Daniel F.

Read (CHANGE/ELP)

Mr. R. P. Gruber (NCUC)

Chapel Hill Public Library 83Q>~ke County Public Library E

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LIST OP OPEN ITEMS/~i

ISSUES, REVIEW BRANCH AND REVIEWER Containment Systems Branch/S.

Huang Open Item 61 Instrumentation and Control Systems Branch/H. Li Open Item 77 t

Power Systems Branch/0.

Chopra Electrical Separation Criteria Issue, Structural Engineering Branch Open Items 335, 336 (7860FXTlcv)

Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report Open Item 61 Supplemental Information The NRC staff indicated that Final Safety Analysis Report (FSAR)

Table 6.2.1-20b and Figure 6.2.1-21 should be revised to reflect the changes identified in discussions between the NRC and CP&L.

~Res onse Carolina Power

& Light Company will revise FSAR Table 6.2.1-20b and Figure 6.2.1-21, as shown herein, in a future FSAR amendment.

(7872PSAlcv)

TABLE 6.2.1-20B LIST OF LEVER ARMS

Volume, Number Lever Arms (ft) relative to nozzle elevation (253.75')

3, 4, 5, 6, 7, 8

9, 10, 11, 12, 13, 14 15, 16, 17, 18, 19, 20 21, 22, 23, 24, 25, 26 27, 28, 29, 30, 31, 32

-24.24

-15.70 8.03

+ 0.92 10.,43 (7864PSAccc)

VOL 31 VOL 30 VOL 29 VOL33 A

VOL27TOVOL31 e B EL 286'0"

'OL 32 EL 268' 15/'I6" EL260'.7/16"

~ Z-Y PLANE (EL. 253.75')

B EL249'13'OL 24 VOL 26 VOL 32

. VOL VOL 28 SECTION AA VOL 27 VOL 19 VOL 18 VOL 17 VOL21 TO VOL 26 C

D VOL3 TO VOL8 VOL2 EL 242'-3/4 VOL 15 TO VOL 20 D

EL 233'-7/16 VOL9 TO VOL 14 EL 225' 13/16" T EL 223'6 VOL 1 VOL 26 VOL 21 VOL 13 VOL 12 X

SECTION B B (EL. 253. 75')

VOL 22 VOL 11 VOL 20 VOL 7

VOL 15 SECTION~

VOL

. 6 VOL 16 VOL 5

PROFILE VIEW (NOT TO SCALE)

EL211'"

< VOL 14 VOL 9

SECTION D.D VOL 10 VOL 8

VOL 3

SECTION E.E VOL 4

{SEE FIGURE 6.2.1-20 FOR ACTUAL COMPARTMENT DIMENSIONS)

PLAN VIEWS (NOT TO SCALE)

SHEARON HARRIS NUCLEAR POWER PLANT Carolina Power 5 Light Company FINALSAFETY ANALYSISREPORT REACTOR CAVITYMODEL ANDCOORDINATE SYSTEM FIGURE 6.2.1.21

Shearon Harris Nuclear Power Plant Draft SER Open Item 77 Supplemental Information The reviewer requested a response to generic letter 83-28, "Salem ATWS Event."

Response

On July ll, 1983, Carolina Power

& Light Company (CP&L) received Generic Letter 83-28, Required Actions Based on Generic Implications of the Salem ATWS events.

CP&L will respond to this letter by November 7,

1983, the required response date.

(7851NECccc)

Shearon Harris Nuclear Power Plant Electrical Se aration Criteria Issue The reviewer requested clarification of, the electrical separation criteria in the cable spreading area as discussed in FSAR Section 8.3.1, pg. 8.3.1-38.

RESPONSE

See attached revision to FSAR Section 8.3.1.

This revision will be included in a future amendment to the FSAR.

(7819NECccc)

o

SHNPP FSAR The minimum separation distance between enclosed raceways or between barriers and the protected raceway(s) is 1 in..

(b)

Cable and Raceway Hazard Areas Analyses of the effects of pipe whip, jet impingement, missiles, fire, and flooding demonstrate that safety related electrical circuits, raceways, and equipment are not degraded beyond an acceptable level.

The analyses are referenced as follows:

High Pressure Piping Missiles Flammable Material Flooding (Section 3 6)

(Section 3')

(Section 9.5.1)

(Section 2.4)

In fire hazard areas outside the cable spreading

rooms, where redundant safety related trays or safety related and non"safety related trays are exposed to the same fire hazard, protection has been provided by spatial separation, fire suppression

systems, fire retardant coatings, fire barriers, or combination thereof.

(c)

Cable Spreading Area and Control Room The cable spreading area is the space below the Control Room where the instrumentation and control cables converge prior to entering the control, termination, or instrumentation panels.

Refer to Section 8.3 1.2. 14 for further discussion of the circuits in these areas.

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<<~er Cable s

eading r ms are n shared b tween Un s.

The c le reading oom for ch Unit separate from tho e of the her Un ts and f other a

as of th lant by hree hou fire wal In t cable s

eading r s, cabl for re dant sa ty divisio s A and are separ ed by th e hour f e barrie Automatic prinkler are also rovided z

the cab spreadi r

s.

Non afety r ted cable are run separat raceways fro safety re ted cab A min um separ ion dist ce of 1 ft.

r trays arated rizontal and 3 f for tray eparate vertical has been tilized.

Where th minimum s

ration stance b

ween sa and no safety r ated systems coul not be

intained, n automa c sprin r system s

utiliz Fire

rriers, closed r

eways, a

or fire etardant atings ve been tilized th a min um separa on dista e of 1

. betwe enclose raceways r betwee barriers nd/or coat s and t protec d racewa s).

The above separation methods are based on the following:

(1)

Cable splices in cable trays are prohibited.

8.3 1-38

INSERT

'A'able spreading rooms are not shared between units.

The cable spreading room for each unit is separated from that of the other unit and from other areas of the plant by three hour fire walls.

In the cable spreading

rooms, cabling for redundant safety divisions A and B are separated by three hour fire barriers.

Automatic sprinklers are also provided in the cable spreading rooms.

Non-safety related cables are run in separate raceways from safety related cables with a minimum separation distance of 1 ft. for trays separated horizontally and 3 ft. for trays separated vertically.

Where the minimum separation distance could not be maintained fire barriers and/or enclosed raceways have been utilized with a minimum separation distance of 1 in.

between enclosed raceways or between barriers and the protected raceway(s).

(7819NECccc)

Shearon Harris Nuclear Power Plant Draft SER Open Item 335 Supplemental Information The reviewer requested verification that in the one-way spring model used for the STARDYNE code in the stability analysis.

requested that a copy of the tme history building be included in the response.

there is no spring disengagement bed rock representation by the In addition, the reviewer plot for the reactor auxiliary

Response

For all computer codes used for seismic dynamic analysis, the model used a

spring that was always in contact with the foundation rock.

The output from the computer consisted of a shear,

moment, and reaction at the foundation level.

Hand computations were made to determine the stability of the structure and the safety factor for sliding and overturning.

To determine the applicability of the spring, a time history plot of the location of the centroid of the vertical reaction is made for the Reactor Auxiliary Building, Unit 1, which has the lowest factor of safety (1.22) against overturning.

There are very few lines crossing the 100 percent contact line which indicate less then 100 percent contact.

A copy of the plot is attached.*

These few lines crossing do not affect the analysis and the safety factors listed.

(7841NLUtda)

• The drawings are being sent to the reviewer only due to their size.

Shearon Harris Nuclear Power Plant Draft SER Open Item 336 Sup lemental Information The reviewer requested that the response contain a commitment to submit the containment structural acceptance test results upon completion.

~Res ouse The containment structure is subject to a preoperational structural proof test as stated in Section 3.8.1.7.1, Structural Integrity Pressure Test.

The pattern of cracks in the structure will be measured before, during, and after the test as stated in the PSAR.

The results of the test will be submitted to the NRC.

The concrete cracking was analyzed using three programs:

SHELL, ANSYS, and EBS/NASTRAN.

The results of the analyses are shown in the attached plot.

The results are all comparable.

(7841NLUtda)

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