ML19257A036
| ML19257A036 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/28/1979 |
| From: | PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19257A034 | List: |
| References | |
| TAC-12654, NUDOCS 7912310520 | |
| Download: ML19257A036 (7) | |
Text
LCA 57 Page 1 of 5 LICENSE CHANGE APPLICATION 57 1.
Page 3/4 8-4 of Appendix A to the Trojan Operating License, Techni-cal Specification Surveillance Requirement 4.8.1.1.2.c should be changed from "... transfers fuel from each storage tank..." to
"... transfers fuel from its associated fuel storage tank...".
2.
a.
Page 3/41-15 of Appendix A to the Trojan Operating License, Technical Specification 3.1.2.7 should be changed as follows:
(1) a.1:
The number "14,418" should be changed to "5000".
(2) b.1: The number "143,374" should be changed to "87,690".
b.
Page B 3/41-3 of Appendix A to the Trojan Operating License, Technical Specification Bases 3/4.1.2 should be changed as follows:
(1) Second sentence of the second paragraph, the numbers "31,200" and "105,374" should be changed to "835 usable" and "9690 usable", respectively.
(2) Two additional sentences should be added to the second paragraph as follows:
"The required boric acid storage tank volume of 835 gallons is below the usable level instrumentation range and thds has been increased to a value on scale (5000 gallons). The required RWST volume of 9690 gallons must be increased to account for nonusable volume due to tank geometry and vortexing considerations (87,690 gallons)."
3.
Table 3.3-3 on Page 3/4 3-18, Table 3.3-4 on Page 3/4 3-24 and Table 4.3-2 on Page 3/4 3-31 of Appendix A to the Trojan Operating License Technical Specifications should be changed from "From Safety Injection Automatic Logic" to " Automatic Actuation Logic".
This change more accuiately reflects the functional unit descriptions.
This is only a clarification in grammar and will not impact the Bases for the Technical Specifications.
4.
Page 3/4 7-27 and Index Page VII of Appendix A to the Trojan Operating License Technical Specification 3/4.7.8.2, snould be changed to include
" spray and/or" before each reference to " sprinkler systems". This change will be consistent with Plant modifications.
5.
Tables 3.3-3 on Page 3/4 3-19a, Table 3.3-4 on Page 3/4 3-24, Table 3.3-5 on Page 3/4 3-27 and Table 4.3-2 on Page 3/4 3-31 of Appendix A to the Trojan Operating License Technical Specifications should be changed as follows:
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LCA 57 Page 2 of 5 a.
An additional function unit, " Auxiliary Feedwater Pumps Start" should be added to the listing of Table 3.3-3, Engineered Safety Feature Actuation System Instrumentation, as denoted on the attached replacement pages.
b.
An additional functional unit, " Auxiliary Feedwater Pumps Start" should be added to the listing of Table 3.3-4, Engineered Safety Feature Actuation System Instrumentation Trip Setpoints, as denoted on the attached replacement pagec.
c.
An additional Initiating Signal and Function, " Steam Generator Water Level -- Low-Low" with appropriate response time and Table Notation should be added to Table 3.3-5, Engineered Safety Features Response Times, as denoted on the attached replacement pages.
d.
An additional functional unit, " Auxiliary Feedwater Pumps Start", should be added to the listing of Table 4.3-2, Engineered Safety Feature Actuation System Instrumentation Surveillance Requirements, as denoted on the attached replacement pages.
Proposed replacement pages are provided for each of the above changes as Attachment A.
REASON FOR CHANGE 1.
Technical Specification 4.8.1.1.2.c currently requires each diesel fuel transfer pump to transfer fuel from either fuel storage tank to the day tanks of both emergency diesels. This capability as described in the existing Technical Specification is not presently available.
The installed cross-connection lines do allow each pump to transfer oil to either day tank but only from their associated storage tank.
This capability satisfies the intent of the design to withstand single failure but a change to the Technical Specifications is necessary to make the surveillance requirement reflect actual as-built conditions.
2.
Detailed calculations indicate that 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 140*F, is 835 usable gal of 7,000 ppm borated water from the boric acid storage tanks or 9,690 usable gal of 2,000 ppm boron water from the RWST.
The present Technical Specification 3.1.2.7 applicable to Modes 5 and 6, requires 14,418 gal and 143,375 gal in the boric acid storage tank and the RWST, respectively. These are the same values as for Technical Specifica-tion 3.1.2.8 applicable in Modes 1, 2, 3 and 4.
It is felt necessary to revise the Technical Specifications to provide correct and updated values where applicable and improve flexibility of Plant operations.
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LCA 57 Page 3 of 5 3.
This Technical Specification change deletes each reference to safety injection actuation as an input to the main steam line isolation logic. Instead, reference to the " automatic actuation logic" is made in each case. This change more accurately reflects the separation between safety injection and main steam line isolation functions.
4.
Trojan Technical Specification 3/4.7.8.2 lists the limiting conditions for operation and surveillance requirements for sprinkler systems in safety-related areas. As part of the Fire Protection System modifica-tions discussed in the Trojan Nuclear Plant Fire Protection Review, PGE-1012 and the March 9, 1978 NRC-issued safety evaluation report (Trojan License Amendment 22), Sprinkler System "J" protecting the electrical penetration area is to be replaced by a water spray or deluge system (designated as spray system 18 and 19 in PGE-1012).
5.
This Technical Specification change adds Auxiliary Feedwater as an engineered safety feature consistent with Trojan FSAR Section 7.3 and recent versions to Standard Technical Specifications for Westinghouse plants.
SAFETY EVALUATION 1.
. Modification of Technical Specification 4.8.1.1.2.c merely reflects the as-built condition of the diesel fuel oil storage and transfer system. This system was designed and constructed in full compliance with the FSAR requirements which provide the bases for the Technical Specifications. As such, this change is merely editorial in nature and involves no new accidents beyond those previously analyzed.
2.
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 and of Mode 6 is 140*F.
The reactor is maintained
>1 percent ak/k shutdown in both modes. Calculated boron-water volumes required to compensate for positive reactivity insertion during cooldown from 200*F to 140*F are 835 gal at 7,000 ppm boron or 9,690 gal at 2,000 ppm boron. These minimum volumes are " usable" values that must be added 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 of the RWST are considered nonusable. Thus, the minimum limit on the RWST should be 9,690 + 78,000, or 87,690 gal. Although the boric acid tanks (BAT) are bottom draining, they have a small unusable volume of 50 gal.
However, the minimum instrument indication volume for the BAT is 4,000 gal. Thus, the limiting value of the BAT should be 50 + 4,000 +
835, or 4,885 gal (approximately 5,000 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 835 gal for the BAT and 9,690 for the RWST were calculated using the following assumption:
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LCA 57 Page 4 of 5 (1) The beginning-of-life (BUL) core reactivity (1,371 ppm for Cycle 2) with the most reactive control rod bank stuck out.
(2) An RCS volume of 12,500 cu ft (the larger the assumed RCS volume, the more conservative the results).
(3) The reactor must be maintained suberitical by at least 1 percent Ak/k.
(4) The RCS temperature reduction is from 200*F to 140*F.
(5) BAT boron concentration is 7,000 ppm.
(6) The RWST boron concentration is 2,000 ppm.
Based upon information available in WCAP-9268, the Nuclear Design and Core Management of the Trojan Nuclear Plant Cycle 2, to maintain a consistent keff (with the same margin of subcriticality) as the RCS temperature decreases from 200*F to 140*F, a boron addition of approx-imately 33 ppm is required. Sensitivity calculations were performed for boron additions ranging from 20-50 ppm as the RCS temperature decreases from 200*F to 140*F.
The results of these calculations indicate that the tank volumes required to borate the RCS with initial RCS boron concentration of 1,371 ppm or less are all less than the minimum volume determined above (835 gal of usable BAT 7,000 ppm borated water, or 9,690 gal of usable RWST 2,000 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 instrumentation indication aspects, all of which were in themselves conservatively calculated.
3.
Modification of Technical Specification Tables 3.3-3, 3.3-4 and 4.3-2 involve only a change in wording to eliminate a potential source of misunderstanding. No physical changes are involved. The Bases to the Technical Specifications are not affected.
4.
Modification to Technical Specification 3/4.7.8.2 has been previously 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.
Discussions of the NRC Staff position and PGE commitments can be found in PGE-1012, Pages C-39 through C-42.
5.
Modification of Technical Specification 3/4.3.2, establishes new operability, setpoints, response time, and surveillance requirements for the Auxiliary Feedwater ( AFW) System, a part of the Engineered Safety Features Actuation System (ESFAS). FSAR Section 6.6.1 describes the design bases for the AFW System, including the time (60 sec) to initate flow following an accident. Section 6.6.2.3.2 describes emergency operation of AFW, including the automatic start signals, or ESFAS, to initiate AFW.
FSAR Section 7.3.1 describes l664 29uB
LCA 57 Page 5 of 5 ESFAS, including portione actuating AFW.
Actuation of AFW is assumed for accident analyses in Sections:
15.2.8 (Loss of Normal Feedwater), 15.2.9
~
(Blackout), 15.3.1 (Small LOCA), 15.4.2.2 (Rupture of a Main Feedwater Pipe), and 15.4.3 (Steam Generator Tube Rupture).
Although FSAR Section 6.6.2.3.2 lists an auto-start of AFW on a loss of both main feedwater pumps, such a start feature is not assumed for any of the accident analyses in FSAR Chapter 15, and thus is considered to be an anticipatory feature not required for mitigation of accidents. For this reason, the loss of both main feed pump auto-start features for AFW is not included in the proposed change.
This Technical Specification change does not affect the FSAR nor does it involve an unreviewed safety question.
SCHEDULE CONSIDERATIONS Since these changes involve relatively insignificant modifications or are editorial in nature, it is hoped that prompt action could be taken and the license amendment received prior to Plant startup following Cycle 3 refueling (by April 1, 1979).
BASIS FOR DETERMINATION OF AMENDMENT CLASS This License Change Application has been de': ermined to result in a Class II License Amendment requiring a fee of $1200. This amendment is felt to be
" pro forma and administrative in nature" which has no safety or environ-mental significance. These changes are consistent with changes made for other nuclear facilities indicating they have been previously reviewed and considered by the NRC.
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