ML18019A829
| 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 0'ACIL:
50-400 Sheav on Hav v is Nuclear Power Plant>
Unit 1.
Cav olina 05000400 AUTH. NAl'lE AUTHOR AFFILIATION ZINYIERNAN>S. R.
Cav olina Power Zc Light Co.
RECIP. NANE RECIPIENT AFFILIATION DENTON, H, R.
Office of Nucleav Reactor Regulation>
Direc tov (post 851125 SUB JECT:
Fov'wav'ds Justif ication of containment isolation HI-1 setpoint pv essure>
v esolving Conf irmatov g Item 13 5 Issue 16 of SER (NUREQ-1038)
Zc NUREQ-0737> TNI Item II. E. 4. 2.
DISTRIBUTION CODE; BOOID COPIEB RECEIVED: LTRi ENCL Q BIIE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 5 Related Cov'respondence NOTES:Application fov pevmit renewal filed.
05000400 REC IP lENT ID CODE/NANE PWR-A ADTS PWR-A EICSB PWR-A PD2 LA BUCKLEY B 01 PWR-A RSB INTERNAL: ADN/LFl'1B IE FILE IE/DGAVT/GAB 21 NRR PWR-A ADTS NRR RQE.M. L NRR/DHFT/NTB RQN2 EXTERNAL: 24X Dl']B/DSS (ANDTS)
NRC PDR 02 PNL GRUEL> R COPIES LTTR ENCL 1
2 2
1 1
2 2
1 1
0 1
1 1
0 1
1 1
3 3
1 1
1 1
1 1
RECIPIENT ID CODE/MANE PWR-A EB PWR-* FOB PWR-A PD2 PD PWR-A PSB ELD/HDS1 IE/DEPER/EPB 36 NRR BWR ADTS NRR PWR-B ADTS N
DHFT/HFIB 04 RN/DDANI/NIB BNL(AMDTS ONLY)
LPDR 03 NSIC 05 COPIES LTTR ENCL 1
1 1
i 1
0 1
1 0
1 0
1 1
1 0
1 1
1 1
TOTAL NUNBER OF COPIEB REQUIRED:
LTTR 34 ENCL 28
H
)k H, l
~
Nj H
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 CONTAINMENTISOLATION 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, GAS/pgp (3939GAS)
Attachment S. R. Z erman Manager Nuclear Licensing Section Cct Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. J. Nelson Grace (NRC-RII)
Mr. Travis Payne (KUDZU)
Mr. Daniel F. Read (CHANGE/ELP)
Mr. R. A. Benedict (NRC)
Wake County. Public Library Mr. Wells Eddleman Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)
Dr. 3. H. Carpenter (ASLB)
Mr. 3. Huang (NRC)
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 willbe 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.
2.
30 5.
6.
Normal Containment Pressure Instrument Span Channel Statistical Allowance Total Channel Inaccuracy Possible Containment Pressure Changes Due to Outside Weather Changes Estimated Internal Pressure Change (i.e., airleaks, etc.) Per Week TOTAL
-0.01 psi 0 to 55.0 psi
+ 2.096
+ 1.32 psi
-.98 psi
.75 psi
-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 willprovide 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 )
J
\\