ML17298A410
| ML17298A410 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/13/1983 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-TM ANPP-24059-WFQ, NUDOCS 8306170326 | |
| Download: ML17298A410 (16) | |
Text
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"AOCE'SSION NBR:8306170326'OCBDATEe 83/06/13 NOTARIZED: YES DOCKET 0'ACIL:STN~50 528 Palo Verde Nuclear Station(
Uni,t 1('rizona Publi 05000528 STN-.50-529 <<Palo Verde Nuclear Station(
Uni,t 2( Arizona Publi
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'STN 50 530,Palo Verde Nuclear Station( Unit <<3( Arizona Publi 05000530 AUTH ~ NAME AUTHOR AFFILIATION VAN"BRUNT(E.E.
Arizona 'P'ubl'ic Ser vice <<Co.
<<RECIP ~ NA'ME<<RECIPIENT AFFILIATION KNIGHTON(G~
Licensing Branch <<3
SUBJECT:
For wards proposed amend >>to FSAR re"CESSAR iodi.ne remoral sys L responses
~to NRC 830422 ltr,Proposed
-FSAR amend combined w/responses close out sump pH issue in "SER Sections 6N4 8
15',8 6,.TMI I-tern II'I'E3',
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TITLE; Licensing 'Submittal:- PSAR/FSAR Amdts 8, Related Correspondence NOTES:Standardized plant>
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Arizona Public Service Company P.O. SOX 21666
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PHOENIX, ARIZONA 65036 June 13, 1983 ANPP-24059 WFQ/RJP Director of Nuclear Reactor Regulation Attention:- -Mr. George Knighton, Chief Licensing Branch No.
3 Division of Licensing U.
S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3
Docket Nos.
STN-50-528/529/530 File:
83-056-026/G.1.01.10
Reference:
(A)
Summary of March 23, 1983 Appeal Meeting on the CESSAR Iodine Removal
- System, from Gary C. Meyer, NRC, dated March 31, 1983.
(B)
Letter from A. E. Scherer, CE, to Darrell G. Eisenhut, NRC, dated April 22, 1983.
Dear Mr. Knighton:
Reference (A) is a
summary of the March'3.
1983 appeal meeting on the CESSAR Iodine Removal System (IRS) ~
Reference (B) transmits CE's revised report
- entitled, "Long-Term Iodine Control in Reactor Containment Buildings Using Combustion Engineering Iodine Removal System" and amendments to the CESSAR-F interface requirements.
In Reference (A),
two plant specific issues were discussed.
1)
Post-accident access to the Spray Chemical Storage Tank (SCST),
and 2) available information to determine the need to reactivate the IRS.
In response to the first issue, the attached amendment to the PVNGS FSAR is proposed.
Also, the following additional information is provided:
NUREG-0737 discusses two cases:
Case 1 postulates a degraded core-intact primary; Case 2,
a LOCA with recirculation via the containment sump.
Case 1:
The iodine removal system would not be operated since iodine release inside the containment is not consistent with the postulated scenario.
830bl7032b 830b13 PDR ADOCK 05000528 E~ ',',,
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I
Director of Nuclear Reactor Regulation ANPP-2405'9
.WFO/RJP Page 2
Case 2:
The assumed core releases are as follows:
Source A = containment airborne (100% noble gases and 25% iodines)
Source C = containment sump (50% halogens and 1% solids)
The direct dose rates from these sources (assuming no decay subsequent to the onset of recirculation [i.e.,
about 20 minutes post-accident))
are 100 mrem/hr to 1,000 mrem/hr within the spray chemical storage tank (SCST)
- room, and 2.5 mrem/hr to 15 mrem/hr along the access corridor to the SCST room.
The bounding scenario airborne does rate (assuming non-ESF ventilation system failure and postulated leakage into the Auxiliary Building in accordance with Regulatory Guide 1.4) builds up to 30 rem/hr in the SCST room after four days post-accident.
Within four days, t'e normal (800 cfm) ventilation system can be restored to service, or, alternatively, a
low volume (50 cfm) purge could be established using portable equipment.
The airborne dose rate can be reduced to less than 3 rem/hr (whole body) within one day 'of low volume purge initiation.
, At this'ose
- rate, PVNGS meets NUREG-0737 (Section II.B.2) dose rate criteria.
By reviewing these bounding scenarios, PVNGS can assure that hydrazine refill capabilities are maintained.
In response to the second
- issue, the following is provided:
I i
The following indicators are available for the operator to choose to reinitiate hydrazine spray:
1) overall radiation level failing to decrease (e.g.,
due to decay)'fter initial injection of hydrazine, 2) subsequent activity release (e.g.,
through operation of the reactor head vent system or safety-relief valves),
3) unexpected decreases in sump pH after four hours post-accident (determined by PASS sample of containment sump),
4) high iodine levels within containment (determined by PASS sample of containment atmosphere
[valid only after 24 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of decay]),
1 t
W H
Director of Nuclear Reactor Regulation ANPP 24059 WFR/RJP Page 3
5) iodine concentration above safety-analysis values (determined by portable monitoring at the site boundary as part of the facility emergency response),
6) elapsed time (when lacking direct or inferred means of determining iodine concentration).
We feel that the attached FSAR amendment, combined with the preceding responses close out the sump pH
- issue, thus allowing the staff to continue with their evaluations of LOCA doses in SER Sections 6.4, 15.4.8, and III.D.3.4.
E. E. Van Brunt, Jr.
APS Vice President Nuclear Projects Management ANPP Project Director EEVB/RJP/wp Attachments cc:
E. Licitra (w/attach.)
A. C. Gehr
Director of Nuclear Reactor Regulation ANPP-24059 HFQ/RJP Page 4
STATE OF ARIZONA
)
) ss.
COUNTY OF MARICOPA)
I, Edwin E.
Van Brunt, Jr.,
represent that I am Vice President, Nuclear Projects of Arizona Public Service
- Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its
- contents, and that to the best of my knowledge and belief, the statements made therein are true.
Edwin E. Van Brunt, Jr.
Sworn to before me this~Q~day o
I 1983.
Notary Public My Commission Expires:
My ConimL<sloa ~res April6. $887
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PVNGS FSAR FISS PRODUCT'REMOVAL AND CONTROL SYSTEMS (B)7.13.21 (B)7.13.22 In the routing of IRS Class IE circuits and location of equipment served by these Class IE Circuits, consideration shall be given to their exposure to potential hazards.
See 7.5 above.
All IRS ASME Boiler and Pressure Vessel Code Section III components shall be arranged to provide adequate clearances to permit inservice inspection.
The design of the arrangement should conform to the guidelines of Section XI of,.the ASME Code.
(B)7.13.23
~uS~rzr g (B)7.13.24 Ac to the IRS shall be provided s that at tim iods greater 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> post-LOCA, capabili refilling the SCST with concentration h
ine son is possible.
Protection shall be provided from internally generated flooding that could prevent per-formance of safety-related functions.
(B)7. 14 (B)7.14.1 WASTE COLLECTION The IRS components are designed for zero external leakage.
In the unlikely event that leakage should occur, provisions shall be provided to accept the maximum leakage rates listed below for purposes of room sump design.
a.
SCAP seals:
b.
Valves backseat leakage:
100 cc/hr/pump 10 cc/hr/inch seat diameter/valve March 1982.
6.5-41 Amendment 8
l lt t)
INSERT A (Excerpt from LD-83-034, dated April 22, 1983)
"Access to the SCST shall be provided following a LOCA such that the concentrated hydrazine solution can be replenished prior to reaching a
minimum level of 5%.
Consideration shall be given to radiological and hydrazine vapor
- hazards, and to alignment of the hydrazine fill apparatus."
PVNGS FSAR FISS PRODUCT REMOVAL AND CONTROL SYSTEMS C'RB)7.13.22 All IRS ASME Boiler and Pressure Vessel Code Section III components are arranged to provide adequate clearances to permit inservice inspection.
The design of the arrangement conforms to the guide-lines of Section XI of the ASME Code.
WjVSGri (RB)7.13.23 (RB)7.13.24 A
to the IRS is provided suc at time pe greater hours post-LOCA, capabi f refilling the SCST wi centrated hydr solu-is possible.
Protection is provided from internally generated flooding that could prevent per-formance of safety-related functions.
Refer also to sections 3.6 and 9.3.3.
(RB)7.14 (RB)7.14.1 WASTE COLLECTION-100 cm /h/pump b.
Valves The IRS components are designed for zero external leakage.
In the unlikely event that leakage should occur; provisions exist to accept the maximum leakage rates listed below for purposes of room sump design.
a.
SCAP seals:
backseat leakage:
across the valve seat:
10 cm /h/in. seat diameter/valve 10 cm /h nominal valve size/valve IRS leakages are treated as potentially toxic waste with a low dissolved solids and organic content.
March 1982 6.5-69 Amendment 8
I
INSERT B
"Access to the SCST is provided following a
concentrated hydrazine solution can be replenished minimum level of 5X.
Consideration is given hydrazine vapor
- hazards, and to alighment of apparatus."
LOCA such that the prior to reaching a
to radiological and the hydrazine fill
1