ML18019A829

Forwards Justification of Containment Isolation HI-1 Setpoint Pressure,Resolving Confirmatory Item 13 & Issue 16 of SER (NUREG-1038) & NUREG-0737,TMI Item II.E.4.2

ML18019A829
Person / Time
Site:	Harris
Issue date:	05/22/1986
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-1038, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM NLS-86-193, NUDOCS 8605280150
Download: ML18019A829 (5)

Text

r r REQUL* 1> INFORNATIQN DISTRIBUTI (STEN (R IDS)

ACCESSION NBR: 8605280150 DOC. DATE: 86/05/22 NOTARIZED: NO DOCKET 50-400 Sheav on Hav v is Nuclear Power Plant> Unit 1. Cav olina 050004000'ACIL:

AUTH. NAl'lE . AUTHOR AFFILIATION ZINYIERNAN>S. R. Cav olina Power Light Co.

Zc RECIP. NANE RECIPIENT AFFILIATION DENTON, H, R. Of fice of Nucleav Reactor Regulation> Direc tov (post 851125 SUB JECT: Fov'wav'ds Justif ication of containment i solation HI-1 setpoint pv essure> v esolving Conf irmatov g Item 13 5 Issue 16 of SER (NUREQ-1038)

DISTRIBUTION CODE; BOOID TITLE: Licensing Submittal:

Zc COPIEB RECEIVED: LTR PSAR/FSAR Amdts 5 filed.

i NUREQ-0737> TNI Item I I. E. 4. 2.

ENCL Q BIIE:

Related Cov'respondence 05000400 NOTES:Application fov pevmit renewal REC IP lENT COPIES RECIPIENT COPIES ID CODE/NANE LTTR ENCL ID CODE/MANE LTTR ENCL PWR-A ADTS 1 PWR-A EB 1 PWR-A EICSB 2 2 PWR-* FOB PWR-A PD2 LA 1 1 PWR-A PD2 PD 1

1 i BUCKLEY B 01 2 2 PWR-A PSB 1 PWR-A RSB 1 1 INTERNAL: ADN/LFl'1B 0 ELD/HDS1 0 IE FILE 1 1 IE/DEPER/EPB 36 1 1 IE/DGAVT/GAB 21 1 NRR BWR ADTS 0 NRR PWR-A ADTS 0 NRR PWR-B ADTS 1 0 NRR RQE.M. L 1 N DHFT/HF IB 1 NRR/DHFT/NTB 1 1 04 1 1 RQN2 3 3 RN/DDANI/NIB 0 EXTERNAL: 24X 1 1 BNL(AMDTS ONLY) 1 1 Dl']B/DSS (ANDTS) LPDR 03 1 NRC PDR 02 1 1 NSIC 05 1 PNL GRUEL> R 1 1 TOTAL NUNBER OF COPIEB REQUIRED: LTTR 34 ENCL 28

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CNK Carolina Power & Light Company MAY 2 2 1986 SERIAL: NLS-86-193 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 - DOCKET NO.50-000 CONTAINMENT ISOLATION HI-1 SETPOINT PRESSURE D'ear Mr. Denton:

Carolina Power R Light Company provides justification of the containment isolation HI-1 setpoint pressure. The attached information resolves Confirmatory Item 13 and Issue Number 16 of Table 16.1 of the Shearon Harris Nuclear Power Plant SER (NUREG-1038). Also, the attached information resolves TMI Item II.E.0.2 of NUREG-0737.

If you have any questions, please contact Mr. Gregg A. Sinders at (919) 836-8168.

Yours very truly, S. R. Z erman Manager Nuclear Licensing Section GAS/pgp (3939GAS)

Attachment Cct Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. 3ohn D. Runkle Dr. J. Nelson Grace (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. 3. H. Carpenter (ASLB)

Mr. R. A. Benedict (NRC) Mr. 3. Huang (NRC)

Wake County. Public Library Mr. 3. L. Kelley (ASLB) 8b05280150 8b0522 PDR ADOCK 05000400 .

E PDR 411 Fayettevitle Street ~ P. O. Box 1551 ~ Raleigh, N. C. 27602

SHNPP SER Confirmatory Item 13 and Issue Number 16, of SER Table 16.1 Containment Isolation Set oint Pressure The applic'ant has not adequately demonstrated that the containment setpoint pressure that initiates containment isolation has been reduced to the minimum compatible with normal operating conditions as detailed in NUREG-0737, Item II.E.0.2, Position 5.

Position The Shearon Harris Nuclear Power Plant (SHNPP) normal containment purge system is a non-safety system designed to maintain the containment at a nominal setpoint of negative 0.25 inches of water gauge (-.01 psi). However, when this system is inoperable, the associated containment isolation valves automatically shut. (This also prevents back flow through the purge make-up lines).

The containment pressure is influenced by events both internal and external to the containment building. It is expected that leakage in the instrument air, breathing air, and service air systems will be the main contributors to containment pressure. External events are normal atmospheric pressure variances of approximately 2 inches of Hg.

(.98 psi) that can cause internal containment pressure to increase. The pressure increase would be caused if the containment was being purged during an atmospheric high pressure front and isolated due to the fail safe design from a fault in the non-safety purge and make-up system and a subsequent passage of an atmospheric low pressure system. This external event could cause an increase in containment pressure by as much as one psi.

Accordingly, the following rationale is applied in justifying the containment HI-1 setpoint pressure:

l. Normal Containment Pressure -0.01 psi

2. Instrument Span 0 to 55.0 psi 30 Channel Statistical Allowance + 2.096 Total Channel Inaccuracy + 1.32 psi

5. Possible Containment Pressure Changes Due to Outside Weather Changes - .98 psi

6. Estimated Internal Pressure Change (i.e., airleaks, etc.) Per Week .75 psi TOTAL -3.05 ps1 The estimated internal pressure change is based on H. B. Robinson II operating experience. Additional pressure increases not included in this estimate are increases due to bulk containment temperature fluctuations within the normal operating band of the containment. An example of this would be during unit startup from cold conditions with the containment temperature at 80'F to power operation with containment temperature at 110'F. In this example, the internal containment pressure would increase approximately .8 psi.

The use of a 3.0 psi HI-1 setpoint is justifiable because it is consistent with NRC guidelines regarding NUREG-0737, Item II.E.0.2, Position 5. As shown above, a 3.0 psi setpoint ensures that the containment HI-1 pressure will provide timely actuation of the underlying safety function thereby assuring consistency with the plant accident analysis and provide operating margin to minimize the potential for spurious actuations.

(3939GAS/pgp )

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