ML20003D965
| ML20003D965 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/11/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18025B411 | List: |
| References | |
| NUDOCS 8104010685 | |
| Download: ML20003D965 (14) | |
Text
.
CN UNITED STATES 8
NUCLEAR REGULATORY COMMISSION h
WASHING TON, D. C. 20555 TENNESSEE VALLEY-AUTHORITY DOCXET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT N0. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendments by Tennessee Valley Authority (the licensee) dated March 22, 1978, as supplemented by letter dated October 10, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The' facility will operate in confamity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the commen defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical. Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility License No. DPR-33 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 70, are hereby incorporated in the 1icense.
The 1icensee shal1 operate the facility in l
accordance with the Technical Specifications.
8104010$ $
. This license amendment is effective as of the date of its issuance.
3.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas ppolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 11,1981.
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s ATTACHMINT TO LICENSE AMENDMENT N0. 70 FACILITY OPERATING LICENSE N0. DPR-33 DOCKET N0. 50-259 4
Revise. Appendix A as follows:
1.
Renove the following page and replace with the identically numbered page:
7] /72 i
2.
The underlined page is the page being changed; the marginal line on this page indicates the revised area. The overleaf page is provided i
for convenience.
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NOTES FOR TABLE 3.2.8 1.
Whenever any CSCS System is required by section 3.5 to be operable, as noted.
If a there shall be two operable trip r.ystems except requirement of the first column is reduced by one, the indicated l
action shall be taken.
If the same function is inoperable in more than one trip system or the first column reduced by more than one, setion 5 shall be taken.
Action:
A.
Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Lf the function is not operable in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, take action B.
8.
Declare the system or component inoperable.
C.
Immediately take action 5 until power is verified on the trip system.
l D.
No action required, indicatots are considered redundant.
2.
In only one trip system.
3.
Not considered in a trip system.
4.
Requires one channel f rom each physical location (there are 4 loca-tions) in the steam line space.
S.
With diesel power, each RNRS pump is scheduled to start immediately and each CSS pump is sequenced to start about 7 sec later.
6.
With normal power, one CSS and one RHRS pump is scheduled to start instantaneously, one CSS and one RHRS pump is sequenced to start after about 7 see with similar pumps starting af ter about 14 sec and 21 sec, at which time the full complement of CSS and RERS pumpe would be operating.
7.
The RCIC and HPCI steam line high flow trip level settings are given in terms of differential pressure. The RCICS setting of 450" of water corresponds to at least 150% above maximum steady state steam flow to assure that spurious isolation does not occur while ensuring the initiation of isolation following a postulated steam line break. Similarly, the HPCIS setting of 90 psi corresponds to at least 150% above maximum steady state flow while also ensuring the initiation of isolation following a postulated break.
8.
Note 1 does not apply to this item.
t 9
The head tank is designed to assure that the discharge piping from the CS and RHR pumps are full. The pressure shall be maintained at or above the values listed in 3.5.1, which ensures water in the discharge piping and up to the head tank.
71 Amendment No. 70
NOTES FOR T A ALE 3. 2.B (Continued) 10.
Only one trip system for each cooler fan.
11.
In only two of the four 4160 V shutdown boards. See note 13.
12.
In only one of the four 4160 V shutdown boards. See note 13.
J 13.
An emergency 4160 V shutdown board is considered a trip system.
14 KRR5W pump would be inoperable. Refer to section 4.5.C for the requirdmente of a RHRSV pump being inoperable.
j 15.
The accident signal is the satisfactory completion of a one-out-of-two taken twice logic of the drywell high pressure plus low reactor pres-sure or the veneel low water level (3, 378" above vessel sero) originating in the core sprey system trip system.
16.
The ADS circuitry is cepeble of accomplishing its protective action with one operable trip system. Therefore one trip system may be taken out of service for functional testing and calibration for a period not to exceed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
72 i
soros UNITED STATES 8
NUCLEAR REGULATORY COMMISSION g
5 p
WASHING TON, D. C. 20555 9,
a
%,..../
TENNESSEE VALLEY AUTHORITY OOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendments by Tennessee Valley Authority (the licensee)datedfiarch 22, 1978, as supplemented by letter dated October 10, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulatic.-
set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
I l
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility License No. DPR-52 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 66, are hereby incorporated in the 1icense.
The 1icensee shal1 operate the facility in accordance with the Technical Specifications.
2-4
'3.
This license amendment is effective as of the date of its issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION'
/
Thomas
. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical-Specifications Date of Issuance: March 11,1981.
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i NOTES FOR TABLE 3.2.8 1.
Whenever any CSCS System is required by section 3.5 to be operable, there shall be two operable trip systems except as noted.
If a requirement of the first column is reduced by one, the indicated action shall be taken.
If the same function is inocerable in more than one trip system or the first column reduced by more than one, action 8 shall be taken.
Action:
A.
Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the function is not operable in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, take action B.
8.
Declare the system or component inoperable.
C.
Immediately take action B until power is verified on the trip system.
D.
No action required, indicators are considered redundant.
2.
In only one trip system.
3.
Not considered in a trip system.
4.
Requires one channel from asch physical location (there are 4 loca-tions) in the steam line space.
S.
With diesel power, each RHRS pump is scheduled to start immediately and each CSS pump is sequenced to start about 7 see later.
6.
With normal power, one CSS and one RHRS pump is scheduled to start 3
instantaneously, one CSS and one RHRS pump is sequenced to start after about 7 see with similar pumps starting af ter about 14 sec and 21 sec, at which time the full complement of CSS and RERS pumps would be operating.
7.
The RCIC and HPCI steam line high flow trip level settings are given in terms of differential pressure.
The RCICS setting of i
l 450" of water corresponds to at least 150% above maximum steady state steam flow to assure that spurious isolation does not occur while ensuring the initiation of isolation following a postulated steam line break.
Similarly, the HPCIS setting of 90 psi corresponds to at least 150% above maximum steady state flow while also ensuring the initiation of isolation following a postulated break.
8.
Note 1 does not apply to this item.
9 The head tank is designed to assure that the discharge piping from the CS and RFR pu=ps are full. The pressure shall be =aintained at or above the values listed in 3.5.1, which ensures water in the discharge piping and up to the head tank.
71 Amendment No. 66
NOTES FOR TARLE 3.2.B (Continusd) 10.
Only one trip system for each cooler fan.
11.
In only two of the four 4160 V shutdown boards.
See note 13.
12.
In only one of the four 4160 V shutdown boards. See note 13.
- 13. An emergency 4160 V shutdown board is considered a trip system.
14 KRR5W pump would be inoperable. Refer to section 4.5.C for the requirements of a RHR5W pump being inoperable.
15.
The accident signs 1 is the satisfactory completion of a one-out-of-two taken twica logic of the drywell high pressure plus low reactor pres-sure or the vessel icw water level (1378" above vessel aero) originating in the core spray system trip system.
16.
The ADS circuitry is capable of accomplishing its protective action with one operable trip system. Therefore one trip system may be taken out of service for functional testing and calibration for a period not to exceed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, l
72
ATTACHMENT TO LICENSE AMENDMENT NO. 66
' FACILITY OPERATING LICENSE NO. OPR-52 DOCKET NO. 50-260
' Revise Appendix A as follows:
- l. -Remove the following page and replace with identically numbered page:
772 2. The underlined page is' the page being changed; the marginal line.on this page indicates-the revised area. The overleaf page is provided for convenience.- 4 S r t 1 F i
pn MGug ,,f + UNITED STATES { g NUCLEAR REGULATORY COMMISSION g C WASHING TON, D. C. 20555 . o, E %,.....,o TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 License No. DPR-68 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for anendments'by Tennessee Valley Authority (the licensee) dated March 22, 1978, as supplemented by letter dated October 10, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this 1icense amendment and paragraph 2.C(2) of Facility License No. OPR-68 is hereby amended to read as follows: (2) Technical Specifications l l l The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 42, are hereby incorporated in the license. The licensee shall operate the facility in i accordance with the Technical Specifications. l i
h 3. -This' license amendment is effective as of' the 'date of its issuance. FOR THE NUCLEAR REGULATORY COMMISSION - /7 .s w Thomas K.'Ippolito, Chief. Operating Reactors Rranch #2 Division of Licensing
Attachment:
. Changes to the Technical i Speci fications ~. l Date of Issuance: March 11, 1981. T T 1 t i t i i t ? I t.. -.... ,.=,__.-_.-._....,..,__,,..,,m.,-.,,,,,_,-_-,,...m,.._
ATTACHMENT TO LICENSE AMEWOMENT NO. 42 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows: 1. Remove the ft llowing page and replace with the identically numbered page: 74 2. The marginal line on the above page indicates the area being changed.
UNIT 3 t10TES FOR TABLE 3. 2. B 1. Whenever any CSCS System is required by section 3.5 to be operable, there shall be two operable trip systems except as noted. If a requirement of the first column is reduced by one, the indicated action shall be taken. If the same function is inoperable in more than one trip system or the first column reduced by more than one, action B shall be taken. Action: A. Repair in 24 hours. If the function is not operable in 24 hours, take action B. B. Declare the system or component inoperable. C. Immediately take action B until power is verified on the trip system. D. No action required, indicators are considered redundant. 2. In only one trip system. 3. Not considered in a trip system. O. Requires one channel from each physical location (there are 4 locations) in the steam line space. S. With diesel power, each RBRS pump is scheduled to start immediately and each CSS pump is sequenced to start about 7 sec later. 6. With normal power, one CSS and one RHRS pump is scheduled to instantaneously, one CSS and one RHRS pump is sequenced start to start after about 7 sec with similar pumps starting after about 14 sec and 21 sec, at which time the full complement of CSS and RHRS pumos would be operating. 7. The RCIC and HPCI steam line high flow trip level settings are given in terms of differential pressure. The RCICS setting of 450" of water corresponds to at least 150% above maximum steady state steam flow to assure that spurious isolation does not occur while ensuring the initiation of isolation following a postulated steam line break. Similarly, the HPCIS setting of 90 psi corresponds to at least 150% above maximum steady state flow while also ensuring the initiation of isolation following a postulated break. 8. Note 1 doei not apply to this item. 9 The head tank is designed to assure that the discharge piping from the CS and RHR pumps are full. The pressure shall be maintained at er above the values listed in 3.5.1, which ensures vater in the discharge piping and up to the hen.d tank. Amendment No. 42 74 .-}}