ML19318A895
| ML19318A895 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/19/1980 |
| From: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19318A893 | List: |
| References | |
| NUDOCS 8006240331 | |
| Download: ML19318A895 (5) | |
Text
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O PORTLAND GENERAL ELECTRIC (X)!!PANY EUGENE WATER & ELECTRIC BOARD AND PACIFIC POWER & LIGHT C0!!PANY TROJAN NUCLEAR PLANT Operating License NPF-1 Docket 50-344 License Change Application 57, Revision 1 This revision to License Change Application (LCA) 57 is submitted in support of Licensee's request to revise certain Limiting Conditions for Operation, Surveillance Requirements and Bases in the Trojan Tech-nical Specificatic,ns (Appendix A to Operating License NPF-1) regarding:
(a) borated water sources; and (b) the Fire Protection System. The other j
amendment previously requested in LCA 57 regarding:
(1) the method of transferring diesel fuel oil from storage to equipment; and (2) change in safety system actuation terminology remains unchanged.
PORTLAND GENERAL ELECTRIC COMPANY By e
C. Goodwin, Jr.
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Assistant Vice President Thermal Plant Operation and !!aintenance Subscribed and sworn to before me this 19th day of June 1980.
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No(ary Publ'ic of Oregon O
!!y Commission Expires:
., 89, sa6A2 8006240 D )
LCA 57, Ravision 1 Pign 1 of 4
_y LICENSE CHANGE APPLICATION 57 1.
-!!odify the below-listed Technical Specifications as shown in Attachment A.-
a.
Technical Specification 3.1.2.7 (Page 3/4 1.-15);
(1).A.1: The number "14,418" should be changed to "5050".
(2) B.1: The number _ "143,374" should be changed to "86,500".
b.
Bases B3/4.1.2 (Page B 3/4 1-3);
(1) Second paragraph, second sentence:
The numbers "31,200" and "105,374" should be changed to "1000 usable" and "8500 usable", respectively.
(2) An additional sentence should be added'to the second paragraph as follows:
"The required Boric Acid Storage Tank volume of 1000 gal is below the usable level l
instrumentation range and thus has been increased to a value on scale (5050 gal).
The required RWST volume of 8500 must be increased to account for nonusable volume due to tank geometry, letdown and vortexing considerations (86,500 gal)."
l 2.
11odify Technical Specification 3.7.8.2 " SPRAY AND/OR SPRINKLER SYSTEM" to include DELUGE SYSTEM; this modification can be done by changing Page 3/4 7-27 and Index Page VII of Appendix A to the Trojan Operating License, Appendix A, Technical Specification from " SPRAY AND/OR SPRINKLER SYSTEMS" to " SPRAY, SPRINKLER AND/0R DELUGE SYSTEM" as shown in Attachment A.
3.
Other amendments previously requested in LCA 57 regarding:
(1) method of transferring diesel fuel oil from storage to equipment; and (2) change in safety system actuation terminology remain unchanged.
_ REASON FOR CHANGE
- 1. - Detailed calculations. indicate the amount of boron required below 200*F sufficient to provide a shutdown margin of 1 percent Ak/k after xenon decay and cooldown from 200*F to below 140*F is 1000 usable gal of 7000 ppm borated water from the Boric Acid Storage Tanks or 8500 usable gal of 2000 ppm borated water from the Refueling Water Storage Tank.
The present Technical Specification 3.1.2.7, appli-cable to Modes 5 and 6, require 14,418 gal and 143,375 gal in the Boric Acid Storage Tank and Refueling Water Storage. Tank, respec-tively, which are the same values for Specification 3.1.2.8, appli-cable in Modes 1, 2, 3 and 4.
Therefore, it is felt necessary to revise the Technical Specifications to provide correct and updated values where applicable and improve flexibility in Plant operations.
Approval of this LCA will'do both.
1
.LCA 57, Rtvision 1 g
Pe gt 2 of 4
- 2. -LCA 57 submitted to the NRC on December 28, 1979, which is pending
'NRC review,_did list the Limiting Conditions for Operations and
. Surveillance Requirements for sprinkler and/or' spray systems in safety-related: areas; however, consideration of a deluge' system was inadvertently omitted.
In the event that any of the spray or Jsprinkler. systems are converted to a deluge system, which is-pref-erable - for some areas, the Technical Specifications should be changed to permit this._ The NRC Guideline Statement (P. 34, D.3)
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in. the Branch Technical Position to the Standard Review Plan 9.5-1, states ~"the preferred acceptable methods for cable spreading room are automatic water system such as closed. head sprinklers, open head deluge, or open directional spray nozzles."
SAFETY EVALUATION
- 1.. This LCA has been reviewed, evaluated and determined to not consti-tute an unreviewed safety question.
No new accidents are created and
.the probability and cons ~equences of accidents previously considered remain unchanged.
No environmental effects or impacts result from
- this LCA.
Technical Specification 3.1.2.7 is applicable only when the Plant is in Operational Modes 5 and 6.
The upper temperature limit of Mode _5 is 200*F; of Mode 6 <140*F.
The reactor is maintained
>l percent ak/k shutdown in both modes.
Calculated boric acid volumes required to compensate for positive reactivity insertion during cooldown from 200*F to possibly as low as 80*F is less than 1000 gal at' 7000 ppm boron or 3500 gal at 2000 ppm boron with no letdown.
These minimum volumes are " usable" values that must be adde'd to tank nonusable volumes due to tank geometry, vortexing considerations or instrumentation spans.
As identified in FSAR Section 6.3.2.2.2, 78,000 gal refueling water storage tanks (RWSTs) are considered nonusable. 'Use of the Boric Acid Storage Tanks (1000 gal) would not require any letdown since the water density will decrease as the temperature decreases from 200*F to 80*F.
Use of.the RWST (3500 gal) may necessitate a letdown flow; thus, an additional'5000 gal will be maintained in the tank. Thus, the minimum limit of the RWST should be 3500 + 5000 + 78,000, or 86,500 gal., Although the Boric Acid Tanks (BAT) are bottom drain-ing.they have~a small nonusable volume of 50 gal.
However, the minimum instrument indication volume is approximately 4000 gal.
Thus, the limiting value of,the BAT should be 50 + 4000 + 1000, or 5050 gal. The present values used in Specification 3.1.2.7 are
-those required for cooldown from normal operating temperature (556*F) to 200*F and are not applicable to this specification for Modes 5 and 6.
The minimum volumes of 1000 gal for the BAT and 3500 gal for the l
RWST were calculated using the differential equations describing constant Reactor Coolant System (RCS) charging mass flow rate with the following assumptions:
E LCA 57, Rivicion 1 g
Pega 3 of 4 Beginning of Life (BOL) core reactivity (1371 ppm) with.
l a.
the most reactive control rod bank stuck out (this is the worst case).
~b.
An RCS water volume of 12,500 cu ft (the larger the assumed RCS volume the more conservative the results).
The reactor must be maintained suberit,ical by at least c.
1 percent ak/k.
d.
The RCS temperature reduction is from 200*F to 80*F.
l e.
BAT boron concentration is 7000 ppm.
f.
The RWST boron concentration is 2000 ppm.
The evaluation was performed by determining, in sequence:
(a) the knount of boron addition required during the appropriate RCS cool-down to maintain subcriticality; (b) the range of applicable initial boron concentrations in the RCS as a function of core burnup; and (c) the required BAT and RWST volumes to maintain subcriticalit'y.
As the RCS temperature decreases from 200*F to 80*F, a boron addition of approximately 66 ppm is required.
Sensitivity calculations were performed for boron additions ranging from 20 to 50 ppm as the RCS temperature decreases from 200*F to 80*F.
The results of these cal-culations indicate that the tank volumes required to borate the RCS with initial RCS boron concentration of 1371 ppm or less, are all less than the minimum volumes determined above (1000 gal of usable BAT 7000 ppm borated water, or 3500 gal of usable RWST 2000 ppm borated water).
Additional conservatism is achieved when these minimum usable volumes are added to the volumes considered nonusable due.to tank geometry, vortexing considerations or minimum instrument indication aspects, all of whch were in themselves conservatively calculated.
This LCA involves changes in limits of boric acid concentrations for BAT and RWST volumes.
The reduction in the limits of these tank volumes has no impact upon the environment..Any reduction in tank volumes, while changing from Modes 1, 2, 3 or 4 to Modes 5 or 6, that result in excess borated water will be disposed of in accord-ance with Environmental Technical Specifications (Appendix B to Facility Operating License NPF-1).
Therefore, the attached Technical Specification change is judged not to impact accident occurrence probability, consequences of Plant safety margins or the environs of the Plant in a deleterious manner.
2.
Modification to Technical Specification 3/4.7.8.2 has been previ-ously reviewed and approved by NRC personnel as part of the Trojan Nuclear Plant Fire Protection Review, PGE-1012, and found to be the most-applicable form of automatic fire water application for this area.
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LCA 57, Rsvision 1 Paga 4 of 4 e-This LCA/ involves only an editorial change 'and does not constitute an unreviewed safety question.
No new accidents are created'and the probability and consequences of accidents previously considered remain unchanged or are reduced.
No environmental effects or impacts resultifrom this LCA.
DETERMINATION OF AMENDMENT CLASS
- 1. -Th'e LCA regarding borated water sources has been determined by the NRC to result in a License Amendment Class III requiring a fee of
-$4,000.
The license amendment resulting from this LCA involves a single safety -issue 'and is not deemed to involve a significant hazards consideration.
2.
1 Rue' LCA regarding the Fire Protection System and other miscellane-ous' changes-has'been determined to result in a Class II License Amendment in accordance with the criteria of 10 CFR 70.22.
This amendment' is insignificant 'and administrative in nature, which has no safety or environmental significance, and-is consistent with the NRC Staff position.
Since-this' amendment involves only minor changes for clarification'and the NRC review of LCA 57 has not been completed yet, it was determined that no fee is required for this amendment and the fee of $1200 previously provided with LCA 57 ehould be applicable for this amendment, KM/mg/4sa6A6
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