ML18018A594
| ML18018A594 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/05/1983 |
| From: | Mcduffie M CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 7134JDK, LAP-83-255, NUDOCS 8307070125 | |
| Download: ML18018A594 (14) | |
Text
REGULATOR NFORMATION DISTRIBUTION 6 I'EM (BIDS)
ACCESSION,NBR:8307070125, DOC.DATE: 83/07/OS.
NOTARIZED:
NO FACIL!S0.400 Shearon Har ris Nuclear Power Planti Unj t li Carol jna
, SO 401 Shearon Harri s Nuclear Power Pl anti Unit 2i Car ol ina AUTH.NAME, AUTHOR AFFILIATION MCDUFFIEiM.A.
Carolina Power L Light Co.
REC IP ~ NAME RECIPIENT AFFILIATION DENTONiH.R.
Office of Nuclear Reactor Reaulationi Director DOCKET 0 000401
SUBJECT:
Forwar ds r esoonses Items 129 through 1
storaae.Aoolicable.
to remainina ooen i
DISTRIBUTION CODE 8001S CO TITLE: Licensina Submittal:
NOTES!
to Auxi 1 iar v Svs Br anch draf t SER Ogen 31 8
137 re agent fuel oogl drainage L
FSAR sections. will be revised.Responses tems forthcominai PIES RECEIVED!LTR
" gr ENCL 'g SIZE PSAR/FSAR Amdts L Related Correspondence RECIPIENT ID CODE/NAME NRR/DI /ADL NRR LB3 LA INTERNAL: ELD/HDS1 IE/DEPER/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFE840 NRR/DHFS/PSRB NRR/DSI/AEB 26 NRR/DSI/CP8 10 NRR/DSI/I CSB 16 NRR/DSI/PSB 19 NRR/OS I/RSB
'23 RGN2 EXTERNAL: ACRS 41 DMB/OSS (AMDTS)
LPDR 03 NSIC 05 COPI'ES LTTR ENCL 1
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3 1
1 1
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2 1
1 1
1 1
1 1
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1 1
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RECIPIENT ID CODE/NAME NRR L83 BC KADAMBIi P 01 IE FILE IE/DEPER/IRB 35 NRR/OE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/OE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/OS I/ASB NRR/OS I/CSB 09 NRR/OSI/METB 12 NRR/
RAB 22 04 RM/DDAMI/MI8 BNL(AMDTS ONLY)
FEMA REP DIV 39 NRC POR 02 NTIS COPIES LTTR ENCL 1
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TOTAL NUMBER OF COPIES REQUIRED:
LTTR 53 ENCL 46
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Carolina Power 8 Light Company JUL pg )g83 SERIAL:
LAP-83-255 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNITS NOS ~
1 AND 2 DOCKET NOS ~ 50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT RESPONSES AUXILIARYSYSTEMS
Dear Mr. Denton:
Carolina Power
& Light Company (CP&L) hereby transmits one original and forty copies of responses to Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report Open Items.
These responses are for the Auxiliary Systems
- Branch, and are CP&L Open Item Numbers
- 129, 130, 131 and 137.
We will be providing responses to other Open Items in the Draft Safety Evaluation Report shortly.
Yours very truly, M. A. McDuffie Senior Vice President Engineering
& Construction JDK/ta (7134JDK)
Attachments cct Mr. N. Prasad Kadambi (NRC)
Mr. N. Wagner (NRC)
Mr. G.
P ~ Maxwell (NRO-SHNPP)
Mr. J.
P. O'Reilly (NRC-RII)
Mr. Travis Payne (KUDZU)
Mr. Daniel P.
Read (CHANGE/ELP)
Chapel Hill Public Library Wake County Public Library 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) 8307070125 830705 PDR ADOCK 05000400 E
PDR 411 Fayetteville Street o P. O. Box 1551
~ Raleigh, N. C. 27602
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DRAFT SER OPEN ITEN 8129 (ASB/NW-2)
Question:
Provide the design of the new fuel storage facility which will maintain k effective equal to or less than 0.95 when considering flooding with non-borated water fire extinguishing aerosols.
~Res oese:
The Shearon Harris Nuclear Power Plant new fuel storage design meets the acceptance criteria of SRP 9.1.1.
When the storage facility is flooded with non-borated water, k effective will be equal to or less than 0.95.
(The SRP also requires that K effective for an optimum moderation situation be equal to or less than 0.98.) In a foam or water mist environment, optimum moderation could be postulated; in this situation, k effective would be equal to or less than 0.98.
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Draft SER 0 en Item No.
130 (ASB/NW-3)
~session:
Explain how draining of the new fuel pool is prevented when spent fuel is being stored.
FSAR page 9.1.3-5 refers to a siphon breaker.
Does the siphon breaker meet single failure criterion?
Also, does the spent fuel pool cooling piping connect to the fuel pool such that the spent fuel/new fuel pool (during storage of spent fuel) water could drain from the pools and uncover spent fuel?
Provide an explanation and figures to indicate piping connections.
~Res onse:
The fuel pool piping elevations do not allow drainage of the pool below the minimum required water level.
The physical arrangement of the piping precludes siphoning of the pools as discussed in FSAR Section 9.1.3.3, Amendment No. 5.
FSAR Figures 9.1.3-1, 9.1.3-2, 9.1.3-3 provide flow diagrams of this piping.
The fuel pool wall elevations at which the lines terminate are as follows:
1.
New Fuel Pool Piping 3SF12-179SA, elevation 279'-6", Nuclear Safety Related (NS) 3SF12-176SB, elevation 279'-6",
NS 3SF12-174SA, elevation 277'-6",
NS 3SF12-171SB, elevation 277'-6",
NS 7SF3-190, elevation 279'-6", Non-Nuclear Safety Related (NNS) 2.
Spent Fuel Pool Piping 3SF12-6SB, elevation 279'-6",
NS 3SF12-5SA, elevation 279'-6",
NS 3SF16-1SA, elevation 278'-6",
NS 3SF16-2SB, elevation 278'-6",
NS 7SF4-218, elevation 279'-6",
NNS 7SF2-218, elevation 279'-6",
NNS 3.
Pool Water Levels Normal water level, 284'-6" Bottom of pool, 246'-0" Top of spent fuel, 260.08'.
Fuel Pool Skimmer System Skimmer hose length, 5'-0", suction piping elevation 285'-3" Skimmer System return piping, elevation 279'-6"
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The failure of this non-seismic Category I, non-nuclear safety class piping provides fuel pool water losses of 5 feet or less.
The water loss from this piping failure has no impact on the conclusions of the heat load calculations and does not affect the required shield water depth for limiting exposures from spent fuel.
Skimmer hose length is required to be limited to 5 feet or less to preclude siphoning of the pool to an unacceptable level.
The SHNPP FSAR will be revised to reflect the above response in a future amendment.
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Draft SER 0 en Item No.
131 (ASB/NW-4)
~oestton:
Provide information to show how spent fuel will be kept cool in the event of a single failure when only Unit 1 is complete and only one pump and one heat exchanger is available to cool the fuel pools, as noted in Section 1.2.3 of the FSAR.
(Section 9.1.3)
~Res onse:
FSAR Section 1.2.3 will be modified in a future amendment to indicate that two Fuel Pool Cooling pumps and two Fuel Pool heat exchangers will be installed for Unit 1 operation.
In the event of a single failure in one of these Spent Fuel Cooling loops, the other loop will provide adequate cooling.
The pool temperature with one Fuel Pool Cooling loop in operation will be equal to or less than 142'F.
(Refer to FSAR Section 9.1.3 for further information.)
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Draft SER 0 en Item No.
137 (ASB/NW-10)
~session:
Identify which heat loads cooled by the CCW are safety related and which are not.
~ses onse:
The heat loads from the following components are considered safety related:
a)
RHR Heat Exchangers b)
RHR Pumps c)
Spent Fuel Pool Heat Exchangers Heat Loads from other components cooled by the CCW, as listed in FSAR Section 9.2.2.2.1, are non-safety related.
FSAR Section 9.2.2.2.1 and Table 9.2.2-3 will be revised to reflect this response in a future amendment.
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