ML18025B566
| ML18025B566 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/29/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18025B567 | List: |
| References | |
| NUDOCS 8107090364 | |
| Download: ML18025B566 (84) | |
Text
LIMITING CONDITIONS FOR OPERATION gl t
- 3. 5.H.
Maintenance of F 'lied Dischar e Pi e The suction of the RCIC and HPCI pumps shall be aligned',to the condensate storage
- tank, and the pressure suppres-sion chamber head 'tank shall normally be aligned to serve the discharge piping of the RHR and'S pumps.
The condensate head tank may be used to serve the RHR and'S discharge piping if the PSC head tank is unavailable.
The pressure indicators on the discharge.of the RHR and CS pumps shall indicate not.less than 3,isted,below.
Pl-75-20 48 psig Pl-75-48 48 psig Pl-74-51
- 48 psig Pl-74"65 48 psig, I.
Average Planar Linear Eleat Generation Rate During steady.state power operation, the Maximum 'Average Pl'anar Heat Generation Rate (MAPHGR) for each type of'uel as a, function of average planar exposure shall not exceed the limiting value shown in Tables 3.5.I-l, -2, -3, -4, and"-5.
If.at any time during operation it is determ'ined by normal surveillance that the limiting,value for APLliGR is:being; exceeded, action shall be
.initiated within 15 minutes to res'tore operation to within the prescribed limits., If the APLHGR is not returned to within the prescribed limits within two (2) hours, the reactor shall'be brought to the Cold Shutdown condition within 36,hours.
Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
J.
Linear lleat Generation Rate (LHGR)
During steady state power operation, the
.'inear heat generation rate (LHGR)'f any rod in any fuel assembly at any axial location shall not exceed the following limits:
SURVEILLANCE REQUIREMENTS 4.5.H Maintenance of Filled Discharge Pipe Every month prior to the testing of the RilRS (LPCI and Containment Spray')
and core spray system, the discharge piping of these syste=s shall be ven'ted 'from the high point and water flow determined."
2.
Following any, period where the LPCI or core spray systems have not been required to be operable, the dis-charge piping of the inoperable sys-tem shall be vented from the hi'gh point prior to the return of.the system to service.
3.
'Whenever the HPCI or RCIC syste= i'
'lined up to take suction from the condensate storage tank;.'the dis-charge piping of the HPCI and RCIC
.shall be vented from the high, poin.
of the system and water flow observe on a monthly basis.
4.
When the RHRS and the CSS are re-quired to be operable, the pressure indicators which mon'tor the dis-'harge lines shall be monitored d'aily and.the pressure recorded.
I.
Maximum Avera e Planar L near Heat Generation Rate (HAPLliGR)
The i~iAPLElCR for each type of fuel as,a
'function of average planar exposu".,e shall be determined.daily during reactor operation at ~ 25/ rated thermal power.
J.
Linear.Heat Generation Rate (LHGR)
The LHGR as a function of core height for 7x7 fuel and as
'a constant for
'8xS,
- SxSR, and PSx8R fuel shall be checked daily during reactor operation at@25% rated.thermal power.
for 8xS,
- Sx8R, and PSx8R fuel 13.4 Kw/ft; for 7x7 fuel, the maximum allowab'e, LHGR as ca1culated by the 'following equation:
8107090364' i0629 PDR ADOCK 05000260 P
'PDR; 159
1.IHITINC CONDITI<<
FOR OPERATION UR LLANCE RE~UIRENE]lTS Q'l(ttt
< l,ll(>ll f 1
'(hl'/l')
(l./l:1')l L))C]t
~ l)csign LllCR ~ 18.3 kW/ft:
d (hp/P)
= Maximum power spiking, penalty
-0026 L ~ Ax>a) post.tron above bottom of core If at any time during operation it is deter, mined by normal surveillance that the limiting valua for L]ICR is being exceeded, action, shall bc i~itiated ~ithin 15 minutes to restore operation to within the prescribed limits.
If the LHCR is not returned to within the prescribed ILaits wirhin two (2) hours, the reactor shall be brought to the Cold Shutdown condition'within 36 hou;s.
Surveillance and corresponding action shal 1 continue until reactor operation is within the prescribed IL.irs.
K.
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Crttical Power Ratio (HCPR)
The YCPR operating l,imi't for BFRP 2 cycle 4 is 1.32 tor 7X7> 1.27 for SXS,
- SxSR, and PSxSR fec)::.
These lir,.its app3.y to steady state po-.
~
wer operation at rated power and flow'.
Eor core flows c>rher than rated, the YCPR shall be ]treater than the above 1dmits t.imes ]<f.
Kf Ls the value shown;in Figure 3>5.2.
K H~nirtuw Cr'tica~
Powe Ra "(o (MCPR)
MCPR s hall be d et ez during reacto powe~
opec at'on at 25X ra ted thermal power. and C
1ollowing any change in power. leve'.
t>r.d'stribution that would cause
'operation with a limiting, control rod pattern a.'desc ibed in the bases for Specificat'inn 3.3.
If at any t:Lme during oper-ation it i's determined by normaI, surveil;I-ance that the limiring value for MCPR is being exceeded, action
. hall be ini.tiated within 15 minutes to restore operation t:o within rhe prescribed lim'ts. If the steady MCPR is not returned to within the pre-scribed limirs with.'n two (2) hours, the reactor shall be brought to t',he Cold Shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, surveillance and corres'ponding action shall con" nue unt'1 reac or operattion is within the prescribed limits.
L.
Pcnor" inc Reouirements I'. any of the limiting values identified in Specifications 3.5.I, 3, or K are exceeded and the, spec'fied action is
- taken, the event shall be I.ogged and reported in a 30-day written report:.
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Docket Nos.'-260 and
-296 I
LlCENSE AUTHQRlTY F>LE C UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 June 19, 1981 DO NOT REMOVE
~go b prg-mz Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanooga, Tennessee 37401 Dear Mr.
Parris:'he Commission has issued the enclosed Amendment Nos. 73,70 and 45 to Facility License Nos.,DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Unit Nos. 1, 2 and 3.
These amendments are in response to your letter of March 21, 1979, as supplemented by your letters of October 4, 1979, October 18, 1979, Nay 19, 1980, June 2, 1980, January 23, 1981, and April 7, 1981.
These amendments modify License Nos.
DPR-33, DPR-52 and DPR-68 to add a condition for you to maintain a Safeguards Contingency Plan to be followed in accordance with 10 CFR 73.40(b) within 30 days of this approval by the Commission.
We have completed our review and evaluation of your Safeguards Contingency Plan and have concluded that the plan for your facility, when fully implemented, will provide the protection needed to satisfy the objectives of the specific requirements of 10 CFR 73.40(b) and 10 CFR 73.55(h) and Appendix C to 10 CFR 73.
We, therefore, conclude that your Safeguards Contingency Plan is acceptable.
I Changes which would not decrease the effectiveness of your approved Safeguards Contingency Plan may be made without approval by the Commission pursuant to the authority of 10 CFR 50.54(p).
A report containing a description of each change shall be furnished to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Comission, Washington, D.C.
20555, with a copy to the appropriate NRC Regional Office within two months after the change is made.
Records of changes made without Commission approval shall be maintained for a period of two years from the date of the change.
These amendments apply to the Safeguards Contingency.Plan and, therefore, do not authorize a change in,effluent types or total amounts nor an increase in power level'nd will not result in any significant environmental impact.
Having made this determination, we have further concluded that these amendments involve an action which is insignificant from the standpoint of environmental impqct and pursuant to 10 CFR 51.5(d)(4) that an environmental impact state-ment, or negative declaratipn and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.
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Hr. Hugh G. Parris Since these amendments apply to the Safeguards Contingency Plan, they do not involve significant new safety information of a type not considered by a previous Commission safety review of the facility.
They do not involve a significant increase in the probability or consequences of an accident, do not involve a significant decrease in a safety margin, and, therefore, do not, involve a significant hazards consideration.
We have also concluded that there is reasonable assurance that 'the health and safety of the public will not be endangered by this actiog and t)at the issuance of these amendments will not be inimical to the commo'n defense and security or to the health and safety of the public.
We will continue tq withhold your Safeguards Contingency Plan and related materials from public disclosure in accordance with the provisions of 10 CFR 2.790(d).
A ~opy o'f the Notice of Issuance is also enclosed.
Sincerely, Encl osures:
1, Amendment No.
~2.
Amendment No.
3.
Amendment,No.
4, No)ice cc w/enclosures:
See next page I
II 73 to DPR-33 70 to DPR-52 45'o DPR-68 Thomas ppoli to, Chief Operating Reactors Branch 82 Divi.sion of Licensing
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Hugh G.'arris CC:
H.
S.
Sanger, Jr.', Esquire General Counsel Tennessee Valley 'Authority 400 Commerce Avenue E 11B 33C
'Knoxville, Tennessee 37902 Hr. -Ron Rogers Tennessee Valley Authority.
400 Chestnut Street, Tower II Chattanooga, Tennessee 37401 Hr. Charl es R. Chri s topher Chairman
.limestone County.Commission P, 0.
Box 188
- Athens, Alabama 35611 Ira L. Nyers, H.D.
State Health Officer State Department of Public Health State Office Building Hontgomery, Alabama 36104 Pr.
H.
N. Culvert 249A HBD 400 Commerce Avenue Tennessee Valley Authority >
Knoxville, Tennessee 37902 Athens Public Library South and 'Forrest
- Athens,
'Alabama 35611 U. S. Environmental Protection Agency Region IV Office ATTN'IS COORDINATOR 345 Courtland Street Atlanta, Georgia 30308 lir. Ro.',ert F. Sullivan U. S. Nuclear Regulatory Comnission P.. 0.
Box 1863
- Decatur, Alabama 35602 Hr. John F.
Cox Tennessee Valley Authority
.W9-D 207C 400 Commerce Ave:;ue Knoxville, Tennessee 37902 Yir. Herbert Abercrombie Tennessee Valley Authority P. 0.
Box 2000
- Decatur, Alabama 35602 Director, Office.of Urban 5 Federal Affairs 108 'Parkway Towers 404 James Robertson Way Nashville, Tennessee 37219
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
'TENNESSEE 'VALLEY AUTHORITY DOCKET'NO; 50-'259 BROMNS
'FERRY "NUCLEAR'PL'ANT;"IjNIT'NO. 1 AMENDMENT TO 'FACIL'ITY 'OPERATING L'ICENSE Amendment No. 73 License No.
DPR-33 1.
The Nuclear Regulatory CommissioII (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licqnsee) dated March 21, 1979, as supplemented by your letters of October 4, 1979, October 18, 1979, May 19, 1980, June 2, 1980, pyIIugry 23
- 1981, and April 7, 1981, complies with, the standards and requiremen(s 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 conformity with the applications, the provisions of the Act, and the rules.and regulations of the Commission; C.
There is reasonable assurance (i ) that the acti,vities authorized by thiq 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, paragraph 2.C. of Facility License No.
DPR-33 is hereby amended by adding subparagraph (11) as'ollows:
(ll) The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Safeguards Contingency Plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p).
The approved Contingency Plan, which was submitted purusant to 10 CFR 73.40, consists of documents withheld from public disclosure pursuant to 10 CFR 2.790(d) and is identified as "Browns Ferry Nuclear Power, Station Safeguards Contingency Plan"'ated March 1, 1979, as revised by page changes dated September 1, 1979, April 15, 1980, 'December 21, 1980, and March 30, 1981, as as may subsequently be revised in accordance with 10 CFR 50.54(p).
The
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Contingency Plan shall be fully implemented, in accordance with 10 CFR 73.40(b) within 30 days of issuance of amendment no. 73 dated June 19, 1981'.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Operating Reactors Branch 82 Divisi'on of.Licensing Date of Issuance:
June 19, 1981
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALL'EY AUTHORITY DOCKET'NO. "50-'260 BROMNS
'FERRY 'NUCL'EAR PLANT 'UNIT NO.
2
'AMENDMENT'TO 'FACILITY'OPERATING 'LICENSE Amendment No. 70 License No.
DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March 21, 1979, as supplemented by your letters of October 4, 1979, October 18, 1979, May 19, 1980, June 2, 1980, January 23, 1)81, and April 7, 1981, 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 ope'rate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commissiqn; C.
Ther's reasonable assurance
('i) that the activities authorized by this amendment can be conducteg 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 isquance 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 ispuance of this amendIIIent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
,Accordingly, paragraph 2.C. of Facility License No.
DPR-52 is hereby amended by adding subparagraph (ll) as follows:
(ll) The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Safeguards Contingency Plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p).
The approved Contingency Plan, which was submitted pursuant to 10 CFR 73.40, consists of documents withheld from public disclosure pursuant to 10 CFR 2.790(d) and is identified as "Browns Ferry Nuclear Power Station Safeguards Contingency Plan" dated March 1, 1979, as revised by page changes dated September 1,
1979, April 15, 1980, December 21, 1980, and March 30, 1981, and
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as may subsequently be revise'd in accordance with 10 CFR 50.54(p).
The Cont'ingency Plan shall be fully implemented in accordance with 10 CFR 73.40(b) within 30 days of issuance of amendment no. 70 dated June 19, 1981.
3.
This 'license amendment is effective as of the.date of its issuance.
FOR'HE NUCLEAR REGULATORY COMMISSION Thomas
. Ippolito, Chief Operating Reactors Branch 82 Division of Licensing Date of Issuance; June 19,
.1981
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHiNGTON, D. C. 20555 TENNESSEE VAL'LEY 'AUTHORITY DOCKET NO. 50-296 BROMNS
'FERRY 'NUCL'EAR PL'ANT; 'UNIT 'NO.
3 AMENDMENT TO FACILITY OPERATING L'ICENSE Amendment No. 45 License No.
DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March 21, 1979, as supplemented by your letters dated October 4, 1979, October 18, 1979, May 19, 1980, June 2, 1980, January 23, 1981, and April 7, 1981, complies with the standards and requirements of the Atomi'c 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 conformity 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 compltance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security'r 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, paragraph 2.C. of Facility License No.
DPR-68 is hereby amended by adding subparagraph (6) as follows:
(6) The li'censee shall fully implement and maintain in effect all provisions of.]he Commission-approved Safeguards Contingency Plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p).
The approved-Contingency Plan, which was submitted pursuant to 10 CFR 73.40, consists of documents withheld from public disclosure pursuant to 10 CFR 2.790(d) and is identified as "Browns Ferry Nuclear Power gtation Safeguards Contingency Plan" dated March 1,
- 1979, as revised by page changes dated September 1, 1979, April 15, 1980, Dedember 21, 1980, and March 30, 1981, and as
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may subsequently be revised in-accordance:with 10 CFR 50.54(p).
The Contingency Plan shall be fully implemented'n accordance with 10 CFR 73.40(b) within 30 days of issuance of amendmen't no. 45 dated June 19,:1981,.
3.
This license amendment is effective as of the date of its issuance.,
FOR THE NUCLEAR REGULATORY COMMISSION Thomas ppolito., Chief Operating Reactors Branch 02 Division, of L'icensing Date of Issuance:
June 19, 1981
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7590-01 UNITED STATES 'NUCL'EAR'REGUL'ATORY 'COMMISSION DOCKET'NOS."'50-'259;'50-260'AND'50-'296 TENNESSEE',VAL'L'EY AUTHORITY NOTICE 'OF'ISSUANCE
'OF 'AMENDMENTS 'TO 'FACILITY
'OPERATING'L'ICENSES The U.S; Nuclear Regulatory Cotwqissjon (the Commission) has issued Amendment No. >> to Facility Operating License No. DPR-33, Amendment No.70 to Facility Operating License No.
DPR-. 52, and Amendment No. 45 to Facility Operating License No.
DPR-'68 issued to Tennessee Valley Authority (the licensee),
which revised Technical Specifications for operation of the Browns Ferry Nuclear Plant, Unit Nos. 1, 2 and 3, located in Limestone County, Alabama.
The amend-ments are effective as of the date of issuance and are to be fully implemented e
within 30 days of Commission 'approval in accordance with the provisions of 10 CFR 73.40(b).
These amendments add a 'conditioq to each of the Facility Operating Licenses to require the licensee to fully implemept and maintain in effect all provisions of the Commission-approved Safeguards Contingency Plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p), within 30 days of the date of these amendments.
The application for the amendments complies with the standards and require-ments of the A'tomic Energy Act of 1954, as amended (the Act), and the Commission's rules and rpgulations, The Commission has made appropriate findings, as required by the Act and the Commission's rules and regulations in 10 'CFR Chapter I, which are set forth in the l.icense amendments.
Prior public t
notice of these amendments was not required since the amendments do not involve a significant hazards consideration.
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7590-01 The Commission has determined that the issuance of these amendments will not result in any significant envi'ronmental impact 10 CFR 551.5(d)(4)
.an environmental impact statement or and that pursuant to negative declaration and environmental impact appraisal need not be prepared in connection with issuance of'. these amendments.
The licensee's application dated Ma'rch 21, 1 979, as supplemented by letters dated October 4, 1979, October 18, 1979, May 19, 1980, June 2, 1980, January 23, 1981, and April 7, 1981 are being withheld from public disclosure pursuant to 10 CFR 2.790(d).
The withheld information is subject to disclosure in accorance with-the pI"ovisions oT'0 CFg
$ 9.12.
For further details with respect to this action,-see (1) Amendment No.73 t'o License No.
DPR-33, Amendment No. 70 to License No.
DPR-52, and Amendment No. 45 to License No.
DPR-68, and (2) the Commission's related letter to the licensee dated June 19, 1981.
These items are available for public'nspection at the Commission's Public Document
- Room, 1717 H Street, N.W.,
!lashington, D. C. and at the Athens Public Library, South and Forrest,
- Athens, A'labama 35611.
A copy of items (1) and (2) may be obtained upon request
'ddressed to the U.S. Nuclear Regulatory Commission, Washington, D.C.
- 20555, Attention:
Director, Division of Licensing.
Dated at Bethesda, Maryland,'his
) 9th day of June 1981
- FOP, THE NUCLEAR REGULATORY COMMISSION omas po ito, Chief Operating Reactors Branch 02 Division of Licensing
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Docket Nos.
5 0-50-296 0
I.ICENSE AUTHORITY FILE O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 June 18, 1981 Mr. Hugh. G. Parris Manager of Power Tennessee Valley Authority 500 A Chestnut Street, Tower II Chattanooga, Tennessee 37401
Dear Mr. Parris:
The Commission has issued the enclosed Amendment Nos.
71, 68 and 43 ta, Facility License Nos.
DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Unit Nos. 1, 2 and 3.
These amendments are in resPoose to your application dated September 9, 1980 (TVA BFNP TS 149),
as supplemented by your letter of February 10, 1981 and subsequent discussions between the NRC staff and your staff.
These changes to the Technical Specifications involve incorporation of certain of the TMI-2 Lessons Learned Category "A" requirements.
These requirements concern (1) Emergency Power Supply/Inadequate Core Cooling, (2) Valve Position Indication, (3) Containment Isolation, (4) Shi.ft Tech-nical Advisor, (5) Systems Integrity Measurements
- Program, and (6) Improved Iodine Measurements Capability.
The changes to the Technical Specification's'ere requested by our generic letter of July 2, 1980 to "All Boiling Water Reactor Licensees."
Copies of the Safety Evaluation and Notice of Issuance are also enclosed.
Sincerely,
Enclosures:
1.
Amendment No.
71 to DPR-33 2.
Amendment No.
68 to DPR-52 3.
Amendment No.
43 to DPR-68 4.
Safety Evaluation 5.
Notice Thoma
. Ippolito, Chief Operating Reactors'ranch b2 Division of Licensing cc w/encls:
See next page
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'Mr. Hugh G. Parris
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CC:
0 H.
S. Sanger, Jr.', Esquire General Counsel Tennessee Valley Authority 400 Commerce Avenue E llB 33C Knoxville, Tennessee 37902 Mr. Ron Rogers Tennessee Val 1 ey Authority 400 Chestnut Street, Tower II Chattanooga, Tennessee 37401 Mr. Charles.
R. Christopher
- Chairman, Limestone County Commission P. 0.
Box 188
- Athens, Alabama 35611 Ira L. Myers, M.D.
State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36104 U. S. Environmental Protection Agency Region IV Office ATTN:
EIS COORDINATOR 345 Courtland Street Atlanta, Georgia 30308 Mr. Robert F. Sullivan U. S. Nuclear Regulatory Comnission P. 0.
Box 1863
- Decatur, Alabama 35602 Mr. John F.
Cox Tennessee Valley Authority W9-D 207C 400 Cori'ce Avenue Knoxville, Tennessee 37902 Mr. Herbert Abercrombie Tennessee Valley Authority P. 0.
Box 2000
- Decatur, Alabama 35602 Yr. H.
N. Culver, 249A HBD 400 Cornerce Avenue Tennessee Valley Authority Knoxville, Tennessee 37902 Athens Public Library South and Forrest
- Athens, Alabama 35611 Director, Office of Urban
& Federal Affairs 108 Parkway Towers 404 James Robertson May Nashville, Terinessee 37219
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROMNS FERRY NUCLEAR PLANT, UNIT NO.
2 AMENDMENT TO FACILITY OPERATING L'ICENSE Amendment No. 68 License No.
DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendments by Tennessee Valley Authority (the 1i'censee).,
dated September 9, 1980, as supplemented by letter dated February 10, 1981, 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 conformity 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 colon 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 Specifi-cations 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 S ecifications The Technical Specifications contained in Appendices.
A and B, as revised through Amendment No.
68, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Techni'cal Specifications.
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This l,icense amendment is, effective, as of the date of,its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION'ttachment:
Changes.
to. the Technical
'Specifications; Date of. Issuance:
June 18, 1981 P'homas.. Ippolito, Chief Operating Reactors Branch, f2 Division of Licensing
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ATTACHMENT TO LICENSE AMENDMENT NO. 68 FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages:
51 79/80
'f697710
,181/T82 367/358 359/380 2.,
The underlined pages.
ave. those. heing changed; marginal.lines on these pages indicate. the area 5eing revised.
Over'leaf pages. are provided for convenience.
3.,
Add the fol.lowing.new page:
105a'..Remove the following page:,
'59a
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6.
Channel shared by 'RPS and. Primary Containment 6 Reactor Vessel'solation Contxol System.
A channel failure may be a channel failure in each, system.
7.
A train i's considered a trip system.
8.,
Two out of three SGTS trains required.
A failure of, more than one will require action A and P
9.
There is only one trip system with auto transfer to two powex'ources.
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Refer to Table 3.7.A and.its notes: for a listing of Isolation Valve Groups and'heir initiating signals.
0 Amendment No.
68
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TABID 3.2+F Surveillance Instrumentation Minimum g of Operable Instrument Clinnnels Instrument //
Instrument Type Indication llotes
.2 IQH 94 ll2M
/6
=
104 Drywell and'Torus Rydrogen Concentration O.l
-, 2Q PdI-64-137 Pdl-64-138 Drywall to Suppression Cl>amber Differential pressure Indicator 0 to 2 paid
'(1) (2)
(3 )
1/Valve Relief Valve Tailpipe Thermocouple Temperature or Acoustic Monitor on Relief Valve Tailpipe Amendment No. X, K, R, 68
(0)
Prom and after the date that, one of these parameters is "educed to one indication, continued operation is permissible during the succeeding thirty days,un'less,such inst umentation is sooner made operable (2)
From and after the date that one of ~these parameter's is not, indicated in the control room, continued operation is permissible during the succe'eding seven days.unless such instrumentation 'is soone:r'ade operahle.,
(>)
Zf the requirements of notes (1) and l(2)i cannot be met, arid if'one of the indications cannot be r'estored, in (6) hours,,
an orderly shutdown shall be initiated and the reactor shall be in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(0)
These su veillance instrnrments are considered to beredundant to each other.
(5) From and after the date. that both the acoustic monitor and the temperature indication on any one valve fails to indicate in the control room, cont:inued operation is permissible during.t;he succeeding thirty days, unless
- one, o:E the two monitoring ch'annels is sooner'ade operable.
If both the primary and secondary indicat:ion on.any SRV tail pipe is inoperable, the, torus t:emperature will be monitored at least once per shi,Et to observe any unexplained temperature increase which might be indicative of an open SRV.
'G.
Amendment No. P:f, 68
TABLE 4.2.F h1INIHUH TEST AND CALIBRATION FREQUEhICY FOR SURVEILLANCE INSTRU/IENTATION Instrument Channel Calibration Frequency Instrument Check 17 Relief valve Tailpipe Thermocouple Temperature NA Once/month (24) 18 Acoustic Honitor on Relief Valve Tailpipe Once/cycle (25)
Once/month (26)
Amendment Ho.
68
~i C
1 0
II
H>","'FS FOR
.ABL..'S 4.2.A THROUGH '4.2.H 1',unct:io>>;il tests shall be performed o>>cc per month.
2.
Functional tests shall be performed before each startup with a required frequ ncy not to exceed once per weel:.
3.
This instrumenta ion is excepted from the func ional test definition.
The:unctiona1 test will consist of injecting a simulated elect ical ign 1 into the -measurement channel.
4.
Tested during lo=ic system functional tests.
5.
Refer to Table 4.1.B.
6.
he logic system functional tests shall include a calibration o..ce per operating cycle of tine delay relays and timers necessary for proper functioning of the trip systems.
7.
The functional test will consist of verifying continunity across the inhibit with a volt-ohmmeter.
8.
Instrument checks shall be performed in accordance with the definition of Instrument Check (see Section '1.0, Definitions).
An instrument check is not applicable to a particular setpoint, such as Upscale; but is a qualitative check that the instrument is behaving and/or indicating in an acceptable manner for the particular plant condition.
Instrument check is included in this table for convenience and to indicate that an Instrument Check will be perform d on the instrument.
Instrument checks are not required when these instruments are not required to be operable or are tripped.
9.
Calibration frequency shall be once/year.
10.
Teste!1 during logic system functional test of SGTS.
ll.
Portion of the logic is functionally tested during. outage only.
The detector will be inserted during each operating cycle and the proper amount of travel into tne core verified.
13.
Functional test will consist of applying simulated inputs (see note 3).
Local alarm lights representing upscale and downscale trips will be verified, but no rod block will be produced at his time.
The inopera-tive trip wi11 be initiated to produce a rod block (SRM and IR>f inoperative also bypassed with the mode'witch in RUIf).
The functions that cannot be verified to produce a rod block directly will be verified during the opera ing cycle.
109
14.
Upscale trip fs functionally tested during tunctional test tfme <<s requited by scctfon 4.7.B.l.a and 4.7.C.l.c.,'5.
The flov bias coaparstoz vill be tested by putting one flov unit in "Tear." (pzoducing L/2 scram) and ad)us'tining the 'teat input co obtain comparatoz rod block.
The flov,bias upscale vill be verified by observing a Local upscale t:rip light during ~operation and verified that ft vill produce a
roc1 block during the operating cycle.
16.
Performed during operacing cycle.
Poztio'ns 'of 'the logic fs checked more frequently during functfonal testa o~f the 'fur!ctfona that produce a rod block.
17.
This calibration consists oi removing the~ fdnctliori ft'.oa'service and pezfozmfng an electronic calibration of the channel.
18.
Functiona.'L eeet fs limited to the cond ftion vhere secondary cont<<inment integrity fs not required as specif Led in'e'cci'ons 3,'7.C.2 and 3,.7.C.3 ~
19.
Functional cesc Ls Lfmited to the time vheze the SCTS fs required to meet the zequfzemencs of section 4.7.C.l.c.
20.
Calibration of che comparacoz requires the fnputs from both recirculation
)oops to be fntezrupted, thereby removing che flov bias sfgnal. to the APRR and I'M and scramming the reactor.
This calibration can only be performed during an outage.
21.
Logic test: is I',Lmfted co the time vhere actual opezation oil the" equfpm!ent's permis<<fblie.
22.
One channel of eithet'he reactor zone'r refueling zone Reactor Bufldfng Ventilation Radiacion Honitorfng Syste*
m!ty be 'adztinf'stratfvely bypassed for a perfod noc to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for. f!~nc'tfoha1'estfng and calfbzatfoh.
'3
'he Reactor Cleanup System Space Temperat!'zze aa'nftozs are RTD's that feed a temperature svfcch Ln che control rohm.~
The 'temper'atuze
'svftch may lbe tested monthly by using a sfmulaced sfgnal.
The RTD itself fs a highly reliable fnstzument and less frequent fesffnII i's n'ece'sssry.
24.
This fnstrument c'heck corisfsts of comparing the, the'zmocouple readings for all valves for con. istence and for nominal expected values (not required during refueling outages).
25.
During each refueling outage, ahull acou. tic monitoring channels shall be calibrate.d.
This cali1bratic>n includes verification of accelerometIer response due. to mechanical excitation in the vfcinity of the sensor.
26.
This instrument c'heck consists of comparing the, background signal ilevels for all valves for consiscency and for nominal expected values (not required during refueling out'ages).
LLO Amendment No.
68
LIHITING CONDITIONS. FOR. 'OPERATION
'SURVEILLANCE REQUIREMENTS 3.6.C Coolant Lczkzre 4.6 ~ C Coo)znc Lezkz c
- 3. If the condition in ) or 2
above cannot be ztec,.an orderly shucdovn shall be initiated and chc reactor she)1 be shut-doMn in thc.Co)d Condi.tion vithin 24.hours.
n.
Relief Valves l..
@hen more than one re1ief valve or one or more safety valves are known to be failed, an orderly shutdown ahal1 bc initiated and the reactor depressurired to lees than 105 paid within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. Relief Valves 1.
At least one safety valve and approxiztate)y one-half of al) relief valves shall be bcnch-chec'ked or rjp)aced vith c bench-checked valve each opera-ting cycle.
All 13'alves (2
safety and'l rc)icf) vill have been cheeked or rcp)aced upon the conc)ction of every second cycle.
2.
Once during each operating
- cycle, each relief valve shall be manually opened until thermocouples and acoustic monitors do~mstream of the valve indicate steam is flo~:ing from the valve.
3 ~
The integrity of the relic!/
safety valve bellovs shall be continuously monitored.
E.
Jet P o.ss A.
At least one relief valve shall bc disasscmb)cd and incpzctcd each opera, ting cycle.
E.
~Jet Pun
~
1.
Mhcncvcr the reactor ia in the ecorcup or run modes, all jet pumps ahzl) be operable.
If is dt cermincd that a ]ec puap is inopcrcb)e, or if tvo or tzore )cc putzp flow instru-sent failures. occur znd can-not be corrected within 12
- hours, zn order)y shucdovn shall bc initiated and che reactor zhz)1 be shutdown in the Co]d Condition within 24 hou ra ~,
1.
Vhenever there is recirculation flow vith the reac or in the startup or run modes vich both recircu)ation pu"ps running,
)et pump operability s'ha)1 be checked'aily by verify'ng ths the fo)loving conditions do noc occur sirtu)taneous)yc a.
The cvo recirculation locps have a flow 1".ha)ance o!
)52 or nore v'hcn cne pu=ps are operated at the sane apeede 181 Amendment No. P, P6.
d8
C.6. E Jet Pi~me b'.
The'ndicated va)ur of ci re flou rate varies fro; thi value derived frcec 1oop flou cirrsurements by oocii than 161.
c.
The diff>> er to lcn:er ply num differential pressure rs'.4-ing on an individual 'el'.
,pump varies free ch= !iran iof all jet pc~ diffreon>>
tisl pressures by more tliin 10Z.
The reactor shall not b operated
<<it?i one recirculaticin',
loop out of so~rice for !sore than 2h hours.
Wit'tx the reactor, opcrat>>Iio, if oiie recircu1etion
~
loop is oui. of ! ervice, t'e plant shall be placed in a hot shutdown con4J.tion <<ith>>n 2lc hours uru.ess tne loop is sooner retu~ied to service.
2,
-Whenever there is recirculst 'cni flow <<1th the reactor in the Startup oc Run Hodr and cnc "e-circulacion punp is opera:.'ii I caILth, the'qucL(z r vr lvi! sir~ed, tice diffuarr co lover pic:nulli d(ffcreIiccfal pcnss<<re shell checked VuI 1-,
and thc dif!er:n-ttal, pressure of an inClvidual Jr:t Iiumlo iic a loc p snail noc
,'vary frori r.he mean of all,'c;t pqmp,uigferencial nressures ln that loi'sp by more than 1GZ.
2.
Fnlloc4ng onc: pimp oper" ion, the discharge valve of'. he lo<<
speed pci.p may not be opene>>L uq.'ess the speed of t'c faster plug is less than
'.0,~ of its rated speed.
3.
Steady state operation with both recirculation punps out of ser-vice for up to. l2 hrs is per-mitted.'urihg such ;interval restart of th. recirculation.
umps is oermitted provided the oop discharge temiierature is within 75oF of the saturation temperature of the reactor vessel water as determined by dome pressure.
The total elapsed time in natural circula-tion and one oump operation must be no greater than 24 nrs.
f:~
5 tr>>c tura1 ') n( grl~t 1.
'I'he accucturul intenrity oC chc priisary systcss shall 'be P.
Jet Pumo Flou I<ismscch
'l. '>>Icixculsclon.pccmp speeds shall be checked'n'd logged at least once per day.
C,Structural I,ncr~rr.1'.tv
- l. 'able'.'f.a Cdjcthei vith sup-plemencsry nor esspccif ies (he j62 Amendment
!90.
54
6 0
ADMINISTRATIVECONTROLS FOOTNOTES l.
A single submittal may be made fo-a multiple unit station.
The submittal should combine those sections tha" are common to all units at the s"ation.
2.
The term "forced reduction in power" is normally defined in
, the electric. power industry as the occurrence of a componen failure or other condition which requires that the load on the uni" be reduced'or corrective,action immediately or up to and including the very next weekend.
Note tha routine ppeyen>
sha13.
be px'esen'-
at the site at aliL.,ines.when there 'is'i>el in tAe zeac or.
20 A, Licensed opera o
shall;be in the control zoom whene~rez there is fuel m 'the x':ea'atter.
3.
A, licensed senior operator sha3.1 be ixi d'-ect charge cc a.. reactor ze, ueling operation; i.e.r able to devote full time to the re.",ueling ope ation.
A health physics technician.shall be present.
at, the facilit3r at al:L t.imes the e.is fuel in the eactor.
5.
Two 1: censed opexata s shall be in the con= al room du ing any cold sta=tups, while shuttinq down the react!or and duzincj recovery fram unit trip.
Either the. plant supezihtend'ent Or "he assistant plan supexintenaent s2iall have aequi ed the experience aria tzaininc; norma'.Lly zeguized fbr examination by the h~C f:or a Senior -Reactor Opera=or'!s License whether o" no" the examination is ta3cer'i. '."n addit'ion, either the operat'ons supewrisor o>> the assi;stant operations supervi:sox; snail have ah SRO~ lichens'e.
A Sh'f t T chnica! Advisor sl:all be present at tha si e at a3.1 times.
6.9 Environmental /uglification A.
By no later than June 30, 1982 a3.1 afety-related electrica3.
equipment in the facility shal:L be qualif:ied ixi accordanice with the provisions of:,
Division oIE Operating Reactors "GuidhlfIned for Evaluatixig Environmental Qualification of Class IE Electrical Equipment in Operating Reactors"
@OR Guidelines); or, NUREG-0588 "Tnterim Staff Position on Environmental Qualification of Safety; Related Electrical Equipment,," December 19,79.
Copies of these documents are attached to Order for Modif:ication of License DPR&2
~
dated October 24, 198Q.,
By no later than December 1, 1980; -complete and auditible.r'ecord's must be avai:Lable and maintained at a central location which describe the environmental q~ualification method used for'all safety-related electrical eq'uipment in sufficient detail,,tq dpcu-'ent the degree.
o/E compliance with the DOR Guidelines or NUREG-
'588.
Thereafter,,
such record:s should be updated and maintained current as equipment i. replaced, further tested, or otherwise furt'<<er qualified.
Amendment Ho.
ke:,~4,4980-68 358
6.10 Inte ritv of Systems Outside Containment A program shall be implemented to reduce leakage rom systems outside
.contaj.nment
.that. would or could contain:.,highly radioactive fluids auring a serious transient or accident to as low as practical leve s.
Tnis program shall Include the following:
1)
Provisions establishing preventive maintenance and periodic visuaI inspection requirements at a frequency not to exceed refueling cycle intervals.
Systems subject to this program are (1) residual heat
- removal, (2) core spray, (3) reactor ~ater cleanup, (4) EPCI, and (5) RCIC.
2)
Syst: em leak test requir'ements, to the extent permitted by system design and radiological conditions, for each system at a frequency in accordance with ASME code section ZI.
The systems subject to this testing are (1) residual heat removal, (2) core spray, (3) HPCI, and (4) RCIC.
- 6. 11 Iodine Honitorin A,pzogram shall Se implemented'hich. will ensure the capability to accurately determine the zirEorne iodine concentration in vital areas*
under accident, conditions.
This program shall include the following:
1)
Training of personnel, 2)
Proceduxes for monitoring, and 3$
Provisions for maintenance of sampling and analysis equipment.
- Azeas reouiring personnel access foT"estab1isning hot shutdown condition.
359
r 0
AO:iI tifSTRA IVE CONTRO!ES TabXe 6.8.A, Minimum shift Crew Reoui ements Shizt Position I
Shift Engineers'SE)
- Units, 1
in G~eration 3
C T~ok of Kic'.enSe'RIO
~
AssiStant Shift Encjineers (AS E) 0 2
SRO Licensed Reactor Operator~
RO Unit Operators (UO)
Assistant Unit Operators (AUO)
'2 6
RO None Shift Technical. Advisor 1
I
one"
!gaea 1th
?h ys ics Technic'ian Ainimun Sh;ift Crew 11 15
&otIe
- 6. 8.A po",ition is normally filled by 'an'assistant. shift
~ncinee but a:s a min,imum it'ay be filled by a, licensed
= actor operator.
When the i'ncL'>mben't is not a senior'actor oerator,,
he shall not be ass5.gled d0ties, re<pairing him'Iv di=ect.
)..icensed ac ivities of reac or operators.
The Shift Technical Advisor shall'have
'a bachelor's degree or, e~'~ui'val'ent'.
in a scientific or engineering discipline with specific training in plant design and transient and accident response and analysis.
'I W~
l Wh
. WO 360 I
Amendment No.
68
~A,IA REeu c~
Np UNITED STATES NUCLEAR REGULATORY COMMISSION
'liYASHINGTON,,D.C. 20555 SAFETY EYALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
'SUPPORTING AMENDMENT NO.
71 TO FACILITY OPERATING LICENSE NO ~ DPR-33 AMENDMENT NO.
68 TO FACILITY OPERATING LICENSE NO.
DPR-52 AMENDMENT NO.
43 TO FACILITY OPERATING LICENSE NO. DPR-68 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT NOS.
1 2 AND 3 DOCKET NOS. 50-259 50-260 AND 50-296 1.0 2.0 Introducti on By letter dated September 9,
1980 (TVA BFNP TS 149), and supplemented by letter dated February 10, 1981, the Tennessee Valley Authority (the licensee or TVA) requested changes to the Technical Specifications (Appendix A) appended to Facility Operating License Nos.
DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, 'Unit Nos.
1, 2 and 3.
The proposed amendments and revised Technical Specifications would incorporate certain of the TMI-2.Lessons Learned Category "A" require-ments.
The licensee's request is in response to the NRC's generic letter "To All Boiling Water Reactor Licensees" dated July 2, 1980.
Back round Information By our letter dated September 13, 1979, we issued to all operating nuclear power plants requirements established as a result of our review of the TMI-2 accident.
Certain of these requirements, designated Lessons Learned Category "A" requirements, were to have been completed by the licensee prior to any operation subsequent to January 1, 1980.
'Our evaluation of the licensee's compliance with these Category "A" items was attached to our letter to the Tennessee Valley Authority dated February 29, 1980 wherein we concluded that TVA had satisfactorily met all Category "A"
requirements.
In order to provide reasonable assurance that operating reactor facilities are maintained, within the limits determined acceptable following the implementation of the TMI.-2 Lessons Learned Category "A" items, we requested that licensees-amend their TS to incorporate additional Limiting Conditions of Operation and Surveillance Requirements, as appropriate.
This request was transmitted to all licensees on July 2, 1980.
Included therein were model specifications that we had determined to be acceptable.
The licensee's application is in direct response to our request.
Each of the issues identified by the NRC staff and the licensee's response is discussed in the Evaluation below.
IO 0
I r
II 0
0
3.0 Evaluation l.
Emer enc Power Su 1 /Inade uate Core Coolin As applicable to Boiling Water Reactors (BWRs), we indicated that water level instrumentation is important to post-accident monitoring and that surveillance of this instrumentation should be performed.
The licensee's response to this request stated that the current surveillance requirements for the reactor. water ~el i'nstrumentation at Browns-Ferry meet or exceed our guidance.
We have reviewed the current specifications (Tables 3.2.A, 3.2.B, 3.2.F, 4.1.A, 4.2.A, 4.2.B and 4.2.F).end determined that water level instrumentation is included.
The specifications provide ACTION state-ments for inoperable instrument channels.
Surveillance requirements for instrument checks and calibration are also included.
The frequency of. surveillance meets or exceeds our guidelines.
Based on this review, we conclude that no changes are required to satisfy our request.
2.
Valve Position Indication Our requirements for installation of a reliable position indicating system for relief and safety valves was based on the need to provide the operator with. a diagnostic aid to reduce the aa15iguity between indications. that might indicate ei'ther an open relief/safety valve or a small line break.
Such a system did not need to be safety grade provided that backup methods of determining valve position are available.
The licensee's request would add both the primary, indicating system (relief valve tailpipe thermocouple temperature detector) and the secondary indicating system (acoustic monitor on relief valve tail-pipe) to the list of surveillance instrumentation in Table 3.2.F that must be available during plant operation.
Since the indicating system provides no automatic action, the licensee proposed that limiting. conditions for operation in the event of an inoperable channel are not appropriate and that the Technical Specifications should be limited to surveillance requirements.
The licensee di'd not present a basis or justification for this position or provide an evaluation of the safety significance of failure of both valve position indicators on any relief valve tailpipe or discuss alternate methods that might be available to control room operators to.diagnose failure of a relief valve to felly seat.
Based on submittals by other licensees, we agree with. the basic premise that there are a number of alternative backup methods for determining that a valve is open.
For example, a periodic check of the torus temperature for any unexplained temperature increase which might be indicative of a stuck open or partially open relief valve would be an acceptable interim action condition.
However, these alternate methods
Il I
I
~ '
~
0
would not provide indications that a valve has reseated.
Therefore, we suggested that the TSs should require at least a primary or backup system of valve position indication to be operable or the reactor should be shutdown after 30 days.
A 30-day limit is con-sistent with current practices for post-accident monitoring instru-mentation.
Accordingly, we find the licensee's submittal as modified by.the HRC staff and agreed to by the licensee to be acceptable.
In the submittal of February 10, 1981, TVA had proposed a monthly check of the valve position instrument channels and a once-per cycle calibration frequency for the acoustic monitors.
These requirements are being added to Table 4.2.F.
We find that the licensee's proposed surveillance requirements on the relief valve position indicators satisfy our guidelines and are acceptable.
Containment Isol ation Our letter of July 2, 1980 indicated that the specifications should include a Table of Containment Isolation Valves which reflect the diverse isolation signal requirement of this Lessons Learned issue.
Table 3.7.A of the Technical Specifications lists the "Primary Containment Isolation Valves" along with -the minimum number required to be operable on each line, the operating characteristics of the valves, their normal position and the action of the valves on the "Primary Containment and Reactor Building Isolation Instrumentation" along with the trip level'ettings and the systems that are isolated when these trip level settings are exceeded.
Based on our review, we have determined that" the current technical specifications satisfy our requirements and'hat no changes are necessary.
However, the licensee proposes to add a note to Table 3.2.A relating this table to Table 3.7.A; the proposed change is acceptable.
Our request indicated that the TSs related to minimum shift manning should be revised to reflect the augmentation of a STA.
The licensee's application would add one STA to each shift to perform the function of accident assessment.
The individual performing this function will have at least a bachelor's degree or equivalent in
- a. scientific or engineering discipline with special training in plant design, and response and analysis of the plant for transients and accidents.
Part of the STA duties are related to operating experience review function.
Based on our review, we find the licensee's submittal to satisfy our, requirements and is acceptable.
il I
~.
4l
Inte rit of S stems Outside Containment Our letter dated July 2, 1980, indicated'hat the license should be amended by adding a license condition related to a Systems Integrity t1easurements Program.
Such a condition would require the licensee to effect an appropriate program to eliminate or prevent the release of significant amounts of radioactivity to the environment via leakage from engineered safety systems and auxiliary
- systems, whi'ch are located outside reactor containment.
The licensee's-application did not address this issue.
Discussions between members of our staffs indicated that (1):the licensee has implemented a leakage reduction program as discussed in TVA's submittal of October 17, 1979 and as reported in our evaluation dated February.29,
- 1980, and (2) the application did not address this issue since TSs are not involved.
The licensee's representatives indicated that they did not object to including. such provisions.
They suggested that they be incorpor-ated into the Administrative Controls Section of the specifications.
Accordingly, we have included the requirements and determined that our request has been satisfied.
Iodine Honitorin Our letter dated July 2, 1980, indicated that the license should be amended by adding a license condition related to iodine monitoring.
Such a condition would require the licensee to effect a program which would ensure the capability to determine the airborne iodine concen-tration in areas requiring personnel access under accident conditions.
The licensee's application did not address this issue.
Discussions between members of our staffs indicated that (1) the licensee has implemented a program to satisfy this i'ssue, as reported in our evaluation dated February 29, 1980.
As discussed in TVA's submittal of October 17, 1979, this program includes the training of personnel, procedures for monitoring, and provisions for maintenance of sampling and analysis equipment; (2) the licensee's application did not address this issue since TSs are not involved'.
The licensee's representatives indicated that they did not object to including such provisions as part of the Administrative Controls Section. of the TSs.
Accordingly, we have included the requirement and determined that our request has been satisfied.
To include this and the above requirement on system integrity, the existing Section 6;9 - "Overall Restoration Coordinator" was deleted.
This position was created following the cable fire which occurred at Browns Ferry on March 22, 1975 to coordinate the restoration work and programs to return Units 1 and 2 to service.
This function has been completed
s 0
0
and the present Section 6.9 is not appropriate.
The present Section 6.10 regarding "Environmental gualification" has been renumbered as-Section 6.9; this, section was-imposed as a separate page by Order dated'ctober 24, 1980.
The above requirements on systems integrity and iodi'ne monitoring were added as Sections 6'.]g and 6.11 respectively.
4.0 Envi'ronmental Consideration We have determined that these amendments do not authorize a change in effluent types-or total amounts nor an increase in power level and will not result in any significant envi,ronmental impact.
Having made this determination, we have further concluded that these amendments involve an action which is. insignificant from the standpoint of envi'ronmental
- impact, and pursuant to 10 CFR Section 51.5(d}(4) that an environmental impact statement, or negative declaration and environmental impact appraisal need not. 5e prepared'n connection with the i'ssuance of these amendments.
5.0 Conclusion We have concluded based on the considerations discussed above that:
(1) because the amendments do not involve a significant increase in the probabi.lity or consequences of accidents previously considered and do not invol,ve a significant decrease in a safety margin, the amendments do
,not involve a significant hazards consideration, (2) thereis reasonable assurance that the.health and safety of the public will not be endangered by operation in the proposed
- manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and'ecurity or to the healthy and safety of the public.
Dated:
June 1 8, 1981
0 II I r~;
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-259, 50-260, AND 50-296 TENNESSEE'VALLEY AUTHORITY NOTICE OF ISSUANCE OF AMENDMEHTS TO FACILITY OPERATING LICENSE The U.
S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 71 to Facility Operating License-Ho.
DPR-33, Amendment No. 68 to Facility Operating License No.
DPR-52, and Amendment No.
43 to Facility Operating License No.
DPR-68.i'ssued to Tennessee Valley Authority (the licensee),
which revimd Technical Specificati'ons for operation of the Browns Ferry Nuclear Plant, Units Hos.
1, 2, and 3, located in Limest'one County, Alabama.
The amendments are effective as of the date of issuance.
These changes to the Technical Specifications involve incorporation of certain of-the TMI-2 Lessons Learned Category "A" requirements.
These require-ments concern. (1) Emergency Power Supply/Inadequate Core Cooling, (2) Valve Position Indication, (3) Containment Isolation, (4} Shift Technical Advisor, (5} Systems Intearity Measurements
- Program, and (6) Improved Iodine 'Measure-ments Capability.
The application for the amendments complies. wi.th. the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
The Commission has made appropriate findings as requi red by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in 'the license amendments.
Prior public'notice of these amendments was not required since the amendments do not involve a significant hazards consideration.
The Comnission has-determined that the issuance of these amendments will not result in any significant. environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration
iO i5
~
J T>
t ik Ck
and'nvironmental impact appraisal need not be prepared in connection with issuance of these amendments.
'For '.further details with respect to this action, see (1) the application for. amendments.
dated, September 9, 1980, as supplemented by letter dated February 10,
- 1981, (2) Amendment No. 71 to License No. DPR-33, Amendment No.
68 to License No. DPR-'2, and Amendment No.
43 to License No. DPR-68,and (3), the Commisston.'s related Safety Evaluation.
All of these items-are available. for public inspection at the Commission's Public Document
- Room, 1717 'H Street, NW., Washington, D.
C.
and at the Athens Public Library, South and Forrest,
- Athens, Alabama 3561.1.
A copy of items (2}'nd (3}, may: be obtained, upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.
C..
20555, Attention:.
Director, Division of Licensing.
'Dated at Bethesda,:Maryland',
this 18 th day of June 1981.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas.
. Ippoli.to, Chief Operating Reactors. Branch,82 Division of Licensing
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i UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 June 15, 1981 Docket Nos,.
50-25
-260 and 5 -296 IPjpg~
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Hugh G. Parri s Manager of Power Tennessee Va'1 1ey Authority 500A Chestnut Street, Tower II Chattanooga, Tennessee 37401
Dear ter. Parris:
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The Commission has issued the enclosed Amendment Nos.
72, 69 and 44 to Facility License Nos.
DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Unit Nos
. 1, 2 and 3.
These amendments are in response to your letter of August 17,
- 1979, as revised by letters dated February 20, 1980, June 2, 1980, October 24, 1980, and April 7, 1981.
The amendments modify the licenses identified above to include a requirement
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to maintain a'Guard Training and gual.ification Plan to be.followed in accordance with 10 CFR 73.55(b)(4) within 60 days of this approval by the Commission.
All security personnel shall be qualified within two years of this approval.
We have completed our review and evaluation of your Guard Training and gualification Plan and have concluded that the plan for these facilities, when fully implemented, will provide the protection needed to satisfy the objectives of the specific requirements of 10 CFR 73.55(b)(4) and Appendix B
to 10 CFR 73.
We, therefore, further concl'ude that your Guard Training and qualification 'Plan is acceptable.
t Changes which would not decrease the safeguards effectiveness of your approved Guard Training and gualification Plan may be made without approval by the Commission.
A report containing a description of each change shall be furnished to the Director, Office of Nuclear Reactor Regulation, U.S.
Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the appropriate NRC Regional Office within two months after the change is made.
Records of changes made without Commission approval shall be main-tained for a period of two years from the date of the change.
These amendments apply to the Guard Training and gualificati on Plan and, therefore, do not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental impact.
Having made this determination, we have further concluded that these amendments involve an action which is insignificant
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Hugh G. Parris 2
from the standpoint of environmental impact and pursuant to 10 CFR 51.5(d)(4) that an environmental impact statement, or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance.,
of these amendments.
Since these amendments apply to the Guard Training and gualification Plan, they do, not involve a significant increase in the probability or conse-quences of an accident, do not involve a significant decrease in a safety margin and, therefore, do not involve a significant hazards consideration.
We have also concluded that there is reasonable assurance that the health and safety of the public will not be endangered by this action and that the issuance of these amendments will not be inimical to the common defense and security or.to the health and safety of the public.
We will continue to withhold your Guard Training and gualification Plan and related materials from public disclosure in accordance with the provisions of 10 CFR 2.790(d).
A copy of the Notice of Issuance is also enclosed.
Sincerely, P
Enclosures:
1.
Amendment No.
72 to DPR-33 2.
Amendment No.
69 to DPR-52 3.
Amendment No.
44 to DPR-68 4.
Notice Operating Reactors Branch 82 Division of Licensing cc w/enclosures:
See next page
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fir. Huoh G. Parris S.
Sanger, Jr.', Esquire General Counsel Tennessee Valley Authority 400 Commerce Avenue E
11B 33C Vnoxville, Tennessee 37902 Yir..Ron Rogers tennessee Yal 1 ey Authority 400 Chestnut Street, Tower II Chattanooga, Tennessee 37401 hr. Charles R. Christopher
- Chairman, Limestone County Commission P.
0.
Box 188
- Athens, Alabama 35611 Ira L. ayers,:N.D.
State Health Officer S ta te'e par tment of Pub 1 ic Hea 1 th State Office 'Building Hontgomery, Alabama 36104
'U. S. Environmental Protection Agency Region IV Office ATTN:
EIS COORDINATOR 345 Courtland Street Atlanta, Georgia 30308 Nr. Robert F. Sullivan U. S. Nuclear Regulatory Commission P. 0.
Box 1863
- Decatur, Alabama 35602 hr, John F.
Cox Tennessee Val.ley. Au:hority W9-D 207C 400 Co&merce Avenue Knoxville, Tennessee 37902 t';r. Herbert Abercrombie Tennessee Valley Authority P.
O.
Box 2000
- Decatur, Alabama 35602 Yr.
H.
N. Culver 249A HBD 400 Cornerce Avenue Tennessee Valley Authority Knoxville, Tennessee 37902 Athens Public Library South and Forrest
- Athens, Alabama 35611 Director, Office of Urban 8 Federal Affairs 108 Parkway Towers 404 James Pobertson Ray Nashville, Tennessee 3721.9
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20055 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259
'BRO>INS FERRY NUCLEAR PL'ANT, UNIT NO.
1 ANENDI1ENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No.
DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 17, 1979, as supplemented by letters dated
'February 20, 1980, June 2, 1980, October 24, 1980, and April 7, 1981,. 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 conformity with the applications, 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 con-ducted 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 o'f the Commission's regulations and all applicable requirements have
,been 'satisfied.
2.
Accordingly, paragraph 2.C of Facility License No.
DPR-33 is hereby amended by adding subparagraph (10) as follows:
(10)
The licensee shall follow all provisions of the NRC approved Guard Training 8 gualificati on Plan, including amendments and changes made pursuant to 1P CFR 50.54(p).
The approved Guard Training 5
gualification Plan is identified as "Browns Ferry Nuclear Power Station Guard Training 5 gualification Plan," dated August 17, 1979, as revised by pages dated January 24, 1980, I~ay 21, 1980, October.
1, 1980, and March 9, 1981 and as may subsequently be
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'revised in accordance with 10 CFR 50.54(p).
The Guard Training
~
8 gual,ification Plan shall be fol-lowed,, in accordance with 10 CFR 73.55(b),
60 days after the date of this amendment.
3.
This license amendment is effective as of the, date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g 0 Thomas~kffppoli o, Chief Operating Reactors Branch II2 Division of Licensing Date of Issuance:
June 15, 1981
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO.'50-260 BRAINS FERRY NUCLEAR PLANT, UNIT NO.
2'NENDllENT TO FACILITY OPERATING LICENSE Amendment No.
69 License No.
DPR-52 e
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 17, 1979, as supplemented by letters dated February 20, 1980, June 2, 1980, October 24, 1980, and April 7, 1981, 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'hapter I; B.
The facility will operate in conformity with the applications, 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 con-ducted 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, paragraph 2.C of Facility License No.
DPR-52 is hereby amended by adding subparagraph (10) as follows:
(10)
The licensee shall follow all provisions of the NRC approved Guard Training 8 gualificati on Plan, including amendments and changes made pursuant to 10 CFR 50.54(p).
The approved Guard Training 5
gualification Plan is identified as "Browns Ferry Nuclear Power Station Guard Training 8 gualification. Plan," dated August 17, 1979, as revised by pages dated January 24, 1980, May 21, 1980, October 1, 1980, and March 9, 1981 and as may subsequently be
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revised in accordance with 10 CFR 50.54(p).
The Guard Training 5 gualification Plan shall he followed, in accordance with 10 CFR
- 73.55(b),
60 days. after the date of this amendment.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas ppolito, Chief Operating Reactors Branch 0'2 Division of Licensing Date.of Issuance:
June 15, 1981
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~pS Rfey P0 n'0,'j UNITED STATES
'NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 TENNESSEE VALL'EY AUTHORITY DOCKET'NO; "50-296 BROIINS FERRY NUCLEAR PLANT, UNIT NO.
3 ANENDl1ENT TO FACILITY OPERATING LICENSE Amendment No.
44 License No.
DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A, The application for amendment by Tennessee Valley Authority (the licensee) dated August 17, 1979, as supplemented by letters dated February 20, 1980, June 2, 1980, October 24, 1980, and April 7, 1981, 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 conformity with the applications, 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 con-'ucted 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'1 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, paragraph 2.C of Facility License No.
DPR-68 is hereby amended by adding subparagraph (5) as follows:
(5)'he licensee shall follow all provisions of the NRC approved Guard Training
& gualificati on Plan, including amendments and changes made pursuant to 10 CFR 50.54(p).
The approved Guard Training gualification Plan is identified ps "Browns Ferry Nuclear Power Station Guard Training 8 l}ualification Plan," dated August 17, 1979, as revised by pages dated January 24, 1980, Nay 21, 1980, October 1, 1980, and 'March 9, 1981 and as may subsequently be
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'evised in accordance with 10 CFR 50.54(p).
The Guard Training 8',qualification Plan shall be followed, in accordance with 10 CFR 73.55(b),
60 days after the date of this amendment.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas A
polito, Chief Operating Reactors Branch 82 Division of Licensing Date of Issuance:
June 15, 1981
II 0
7590-01 UNITED "STATES 'NUCL'EAR 'REGULATORY COMMISSION DOCKET'NO:'50-259, 50-'260 AND'50-296 T NNESSEE VALLEY AUTHORITY NOTICE OF ISSUANCE OF AMENDMENTS TO'FACILITY OPERATING L'ICENSES The U.S.
Nuclear. Regulatory Commission (the Commission) has issued Amendment No.
72 to Facility Operating License No DPR-33, Amendment No.
69 to Facility Operating License No.
DPR-52 and Amendment No. 44 to Facility Operating License 'No.
DPR-68 issued to Tennessee Valley Authority (.the licensee.);
which revised the licenses for operation of the Browns Ferry Nuclear Plant, Unit clos. 1, 2 and 3, located in Limestone County, Alabama.
The amendments are effective as of the date of issuance and are to be fully implemented within 60 days of Commission approval in accordance with the provisions of 10 CFR 73.55(b)(4).
These amendments add a condition to each of the Facility Operating Licenses to, require the licensee to follow al.l provisions of the Commission approved Guard Training and gualification Plan, including amendments and changes made pursuant to 10 CFR 50.54(p), within 60 days of the date of these amendments.
The application for the amendments complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
The Commission has made appropriate findings as required by the Act and the Commission's rules.and regulations in 10 CFR Chapter f, which are set forth in the 1'icense amendments.
Prior public notice of these amendments was not 'required si nce the amendments.
do not involve a significant hazards consideration.
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7590-.01
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The Commission has determined that the issuance of these amendments will not result in.any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration and
,environmental impact appraisal'eed not be prepared in connection.with issuance of these amendments.
The 'licensee's filing dated-August 17, 1979, as supplemented by letters dated February 20, 1980, June 2, 1980, October 24, 1980, and April 7, 1981 are being withheld from public disclosure pursuant to 10 CFR 2.790(d).
The withheld informa-tion is subject to disclosure in accordance with the provisions of~10 CFR 59.12.
For. further detai,ls with,,respect to this action, see,(l)
Amendment No.
72 to Picense No DPR-33, Amendment No. 69 to 'License-No.
DPR-52, and Amendment No. 44 to License No.
DPR-68 and (2) the Commission's letter to the licensee dated 6/15/81 These items are available for public inspection at the Commission's
-.Public Document
- Room, 1717
'M Street, N.W., Washington, D.C. and at the Athens Pub1ic Library, South and Forrest,Athens, Alabama 35611.
A copy of items (1-)
and (2)
- may, be obtained.'pon request addressed to the U.S. 'Nuclear 'Regulatory Commission, Washington; D.C.
20555, Attenti'on:
Director,'ivision of Licensing.
Dated at Bethesda,,
tiaryland,. this 15th day of June 1981.
FOR THE NUCLEAR'EGULATORY COMMISSION Thoma
. Ippol ito, Chief Operating Reactors Branch ¹2
. Division of Licensing
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