ML20113G144
| ML20113G144 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/16/1985 |
| From: | Nash B GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC |
| References | |
| NUDOCS 8501240259 | |
| Download: ML20113G144 (5) | |
Text
.
UNIT 1 LICENSE / TECH. SPEC. CHANGE INSTRUCTION MD40 1
CORRECT ADDRESS
+
U. S. NUCLEAR REG. COMMISSION IF NECESSARY LICENSING DEPARTMENT WASHINGTON, DC 20555 IqETW4N TO: Betty Nash U 37 Procedure Distribution Control i
Unit 2 Admin. Bldg.
Date 1-1L-85 Please i.pdate your Unit 1 Technical Specifications with the attachments as instructed below. Also, please sign the acknowledgment at the bottom of this memo and return to Setty Nash at the address shown above.
.1,. License Ammendment Nunbar 103
_, Order for Nodification of License Remove Insert Accendix Section Pice No.
Amendment Pace No.
Amendment 3,4k6,6a,7 3,d,'h,'h"6a,6 b,7 License 102 103 Table of Effective Pages A
3 3-100 7?
3-100 103 A
3 3-101 72 3-101 103 A
3 3-102 72 3-102 103 A
3 3-103 72 3-103 103 A
3 3-104 72 3-104 103 A
3 3-105a 72 3-105a 103 A
4 4-81 91 4-81 103 l
l 8501240259 850116 DR ADOCK 05000
=
ADDITIONAL INSTRUCTIG4S/CO M TS Amendment 103 was issued 12-21-84 and received 01-03-85 as a result of l
conditions imposed by t.e ASLB and became effective as of tne
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date of issuance (12-21-84).
The entire comratino License is aIso beina issued with this amendment.
I 1
I hereby ackncaledge receipt of the items above and have complied with tN l
instructions.
l (Signature)
(Ext. No.)
(Data)
A0000482 6-81
TMI-1 TECHNICAL SPECIFICATIONS PAGE 1 0F 4 APPENDIX A TABLE OF EFFECTIVE PAGES PAGE REV.
PAGE REV.
!I i
72 3-11 i
11 98 3-12 47 111 81 3-13 4-20-81 iv 97 3-13a 4-20-81 y
77 3-14 vi 100 3-15 17 v11 72 3-15e 4-20-81 viii 77 3-16 45 3-17 4
1-1 3-18 1-2 98 3-18a 1-3 3-18b 42 i
1-4 3-18e 78 1-5 36 3-18d 78 1-6 72 3-18e Deleted 1-6a 72 3-18f 97 4
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1-7 72 3-18g 97 1-8 72 Fig. 3.1-3 3-19 98 3-20 50 t
2-1 17 3-21 98 2-2 90 3-22 98 2-3 50 3-23 2-4 78 3-24 80 Fig. 2.1-1 50 3-25 98 l
Fig. 2.1-2 50 3-26 78 Fig. 2.1-3 50 3-26a 78 2-5 28 3-27 93 2-6 50 3-28 78 i
2-7 78 3-29 78 2-8 78 3-30 78 2-9 90 3-31 78 Fig. 2.3-1 78 3-32 78 Fig. 2.3-2 50 3-32a 78 3-33 17 l
3-34 90 3-1 98 3-34a 50 l
3-la 98 3-35 50 t
3-2 47 3-36 50 3-3 29 3-36a 39 3-4 29 Fig. 3.5-2A 50 i
Fig. 3.1-1 29 Fig. 3.5-28 50 l
Fi 29 Fig. 3.5-2C 50 3 g. 3.1-2 5
29 Fig. 3.5-2D 50 3-6 78 Fig. 3.5-2E 50 3-6a 78 Deleted 50 j
3-7 78 Fig. 3.5-26 90 3-8 Fig. 3.5-2H 50 3-9 3-37 89 3-10 3-37a 89 navision 0 unless otherwise indicated l
Amendment 103
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PAGE 2 0F 4 PAGE REV.
PAGE R_ V.
E 3-38 3-86 100 i
3-39 3-87 101 3-40 3-87a 101 3-40a 100 3-88 32 3-40b 100 3-89 101 3-40c 78 3-90 101 3-40d 3-91 101 3-40e 100 3-92 101 Fig. 3.5-1 3-93 101 3
Fig. 3.5-2 3-94 101 Fig. 3.5-3 3-95 59
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3-41 102 3-95a 81 l
3-41a 87 3-95b 81 3-42 3-95c 81 3-43 98 3-96 88 3-44 27 3-97 88 3-45 3-98 72 3-46 64 3-99 88 3-47 to 3-54 Deleted 3-100 103 3-55 48 3-56 48 3-56a 48 3-101 103 3-57 3-102 103 3-58 3-103 103 3-59 3-104 103
'0 3-60 3-105 78 3-61 76 3-105a 103 3-62 55 3-106 72 3-62a 76 3-107 72 3-62b 55 3-108 72 3-62c 76 3-109 72 3-62d 55 3-110 72 l
3-63 30 3-111 72 3-64 30 3-112 72 1
3-65 94 3-113 72 3-66 94 3-114 72 3-67 61 3-115 72 3-68 61 3-116 85 i
3-69 94 3-117 72 l
3-70 30 3-118 72 l
3-71 61 3-119' 72 3-72 30 3-120 72 3-73 30 3-121 72 3-74 30 3-122 72 3-75 30 3-123 72 3-76 30 3-124 72 3-77 30 3-125 72 3-78 30 3-126 72 3-79 61 3-1 27 72 3-80 75 i
3-81 41 3-82 to 3-85 Blank l
i Amendment 103 l
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PAGE 3 0F 4 PAGE REV.
PAGE REY.
4-52 78 4-1 l')0 4-52a 78 4-2 7L 4-52b 78 4-2a 78 4-53 4-3 102 4-54 97 4-4 47 4-55 68 4-5 78 4-55a 55 4-5a 100 4-55b 68 4-6**
24 4-55c 55 4-7 80 4-55d 76 4-7a 78 4-55e 55 4-8 78 4-56 64 4-9 95 4-57 Blank 55 4-10 95 4-58 4-10a 100 4-59 65 4-11 71 4-60 30 4-12 11-2-81 4-61 30 4-12a 11-2-81 4-62 30 4-13 60 4-63 to 4-71 Blank 32 4-14 to 4-27 Blank 54 4-72 101 Fig. 4.2-1 Deleted 54 4-73 32 4-27a 60 4-73a 32 4-28 4-73b 32 4-29 63 4-73c 32 4-30 27 4-74 32 l
4-31 63 4-75 101 4-32 93 4-76 32 4-33 93 4-76a 101 4-34 63 4-77 47 4-34a 63 4-78 47 4-34b 93 4-79 47 4-35 95 4-80 86 4-35a 59 4-81 103 4-36 59 4-82 86 4-37 55 4-83 47 4-38 4-84 47 4-38a 87 4-85 86 3-39 78 4-86 47 4-40 70 4-87 72 4-41 68 4-88 88 4-42 68 4-89 72 4-43 4-90 72 i
4-44 68 4-91 72 4-45 4-92 72 4-46 70 4-93 72 4-47 78 4-94 72 4-48 4-95 72 l
4-49 4-96 72 4-50 4-97 72 4-51 95 4-98 72 lO l
Amendment 103 I
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PAGE 4 0F 4 PAGE REY.
PAGE REY.
i 4-99 88 6-6 77 4-100 72 6-7 84 6-8 99 6-9 99 4-101 72 6-10 77 3
4-102 72 6-11 84 4-103 72 6-12 77 4-104 72 6-13 82 l
4-105 72 6-14 77 4-106 72 6-15 77 4-107 72 6-16 77 l_
4-108 72 6-17 77 4-109 72 6-18 77 4-110 72 6-19 77 4-111 72 6-20 77 4-112 72 6-21 77 4-113 72 6-22 102 4-114 72 6-23 102 i
4-115 72 6-24 77 4-116 72 Fig. 6-1 92 4-117 72 Fig. 6-2 79 4-118 72 4-119 72 4-1 20 72 4-121 72 4-122 72
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PUNISYLVANIA ELECTRIC C(BIPANY GPU NUCLEAR CORPORATION D0CKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT N0. 1 APENOMENT TO FACILITY 0PERATING LICENSE Amendment No.103 i
License.No. DPR-50 1.
The Nuclear Regulatory Coeurission (the Ccamission) has found that:
A. The application for amendment by APU Nuclear Corporation, et a1 (the licensees) dated May 9, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended 2
(the Act) and the Coeurission's rules and regulations set forth in 10 CFR Chapter I;
- 8. The facility will operate in conformity with the application, the provisions of the Act, and the mies and regulations of the Caumission; C. There is reasonable assurance (1)' that the activities authorized by this amendment can be conducted without endanpring the health and safety of the public, and (11) that such act'vities will be conducted in compliance with the Casurission's regulations; D. The issuance of this amendment will not be inimical to the cosmon defense and security or to the health and safety of the public; and E. The issuance of this amanht is in accordance with 10 CFR Part 51 of the Casurission's regulations and all applicable requirements have been satisfied.
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Accordingly Facility Operating License No.'DpR-50 is hereby amended as indicated below and >y changes to the Technical Specifications as indicated in the attachment.to this Itcense amendment.
A.Reviseparagraph2.c.(2)toreadasfollows:
Technical Soecifications Tha Technical Specifications contained in Appendix A, as revised through Amendment No.103, are hereby inccrporated in the license. The GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
B. Revise paragraph 2.c..(8) to read as follows:
Reoaired Steam Generators In order to confim the leak-tight integrity of the Reactor Coolant System, including the steam generators, operation of the facility shall be in accordance with the following:
1
- 1. Prior to initial criticality, GPU Nuclear Corporation shall submit to NRC the results of the steam generator hot test program and a sussary of its management review.
iO
- 2. GPU Nuclear Corporation shall confim the baseline primary-to-secondary leakage rate established during the steam generator hot test program.
If leakage exceeds the baseline leakage rate by more than 0.1 GPN, the facility shall be shut down and leak tested.
If l
any increased leakage above baseline is due to defects in the tube free span, the leaking tube (s) shall be removed from service. The baseline leakage shall be reestablished, provided that the leakage limit of Technical Specification 3.1.6.3 is not exceeded.
- 3. GPU Nuclear Corporation shall complete its post-critical test program ateachpowerrange(0-55,55-505,505-1005) in conformance with the program described in Topical Report 008. Rev. 3 and shall have available the results of that test program and a summary of its management review, prior to ascension from each power range and prior
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to nomal power operation.
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- 4. GPU Nuclear Corporation shall conduct addy-current examinations, consistent with the extended inservice inspection plan defined in i
Table 3.3-1 of NUREG-1019, either 90 calender days after reaching full power, or 120 calendar days after exceeding 505 power operation, whichever comes first. In the event of plant operation for an extended period at less than 505 power, GPU Nuclear Corporation shall provide an assessment at the end of 180 days of operation at power levels between 55 and 505, such assessment to contain recessendations and supporting infomation as to the necessity of a special eddy-current testing (ECT) shutdown before the end of the refueling (The NRC staff will evaluate that assessment and detemine the cycle.
time of the next addy-current examination, consistent with the other provisions of the license conditions.) In the absence of such an assessment, a special ECT shutdown shall take place before an additional 30 days of operation at power above 55.
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- 5. GPU lluclear Corporation shall ' provide routine reporting of the
.long-ters corrosion " lead tests" test results on a quarterly basis
.. as weil as more timely notification if adverse corrosion test results-
- are discovered.
j 3.
This license amendment is effective as of the date of its issuance.
THE IlUCLEAR RE TORY CWelI55!0N 7
i F. Stolz, Chief rating Reactors 8r
- 4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 21,1984 l
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UNITED STATES
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NUCLEAR CE2ULATORY COhitilSSION 3
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IETROPOLITAN EDISON COWANY JERSEY CDmtAL POWER AND LIGHT COMPANY P NNSYLVANIA ELECTRIC CDWANY GPU NUCLEAR
- CORPORATION (Three Mile Island Nuclear Station. Unit 1)
D0CKET NO. 50-289 FACILITY OPERATING LICENSE 1.
The Atomic Energy Commission (the Commission) having found that :
I a.
The application for license filed by the Metropolitan Edison Company. Jersey Central Power and Light Company, the Pennsylvania Electric Company. (the owners) complies with the standards and l
requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Consission's rules and regulations set forth in 10 CFR Chapter 1 and all required notifications to other agencies or bodies have been duly made; b.
Construction of the Three Mile Island Nuclear Station. Unit 1 (the facility) has been substantially completed in confcmity with Construction Permit No. CPPR-40, the application, as amended, the provisions of the Act and the rules and regulations of the Comission; c.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Coanission; d.
There is reasonable assurance:
(1) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Comission; e.
GPU Nuclear Corporation is technically qualified and the owners t
are financially qualified to engage in the activities authorized by this operating license in accordance with the rules and regulations of the Comission;2 IThese findings are virtually of no present significance. The license authorizing GPU Nuclear to operate Tril. Unit 1. is suspended pending the outcome of the Tlil-1 restart proceeding. That proceeding will detemine whether GPU Nuclear is qualified to operate the facility.
Issuance of an amendment, dated September 23. 1931 authorizing GPU O
Nuclear to assume the prior responsibility of liet Ed under the license, is not intended to influence or otherwise prejudice that proceeding.
I See note 1 above.
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- f. The owners have".
satisfied the applicable provisions of 10 CPR
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Part 140 " Financial Protection Requirements and Indemnity Agressants." of the Commission's regulattems; 3
The issuance of this operating Ifconse will not be inimical to the common defense and security or to the health and safety of the public
- 4. After weighing the environmental, economic, technical, and oth'er benefits of the facility against environmental costs and considering available alternatives, the issuance of Facility Operating License Ito. DPR-50 is in accordance with 10 CFR Part 50. Appendix 0, of the Commission's regulations and all applicable requirements of said Appendix D have been satisfied; and 1.
The receipt, possession, and use of sourca. byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70 including 10 CFR Section 30.33, 40.32. 70.23 and 70.31.
2.
Facility Operating License No. DPR-50 is hereby issued to the Metropolitan Edison Company, Jersey Central Power and Light Company.
Pennsylvania Electric Company and GPU Nuclear Corporation to read as follows: l l
a.
This license applies to the Three Mile Island Nuclear Station. Unit 1 a pressurized water reactor and associated equipment (the facility).
l owned by the Metropolitan Edison Company. Jersey Central Power and l
l Light Company. Pennsylvania Electric Company and operated by GPU Nuclear Corporation. The facility is located in Dauphin County.
Pennsylvania and is described in the " Final Safety Analysis Report" as supplemented and amended (Amendments 1 through 47) and the Environmental Report as supplemented and amended (Amendments 1 and 2).
b.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) GPU Nuclear Corporation, pursuant to Section 104b of the Act l
and 10 CPR Part 50 " Licensing of Production and Utilization Facilities." to possess, use, and operate the facility 3; and Metropolitan Edison Company, Jersey Central Power and Light l
Company and Pennsylvania Electric Company to possess the facility e in accordance with the procedures and limitations set forth in this license; (2) SPU Nuclear Corporation, pursuant to the Act and 10 CFR l
Parts 30, 40 and 70 to receive possess and use at any time any byproduct, source and special nuclaar material as reactor fuel, sealed neutron sour:es for reactor startup, sealed O
sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required for reactor operation; 3
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Pap 5 (3)
SPU Nuclear Corporation pursuant to the Act and 10 CFR Part O
- 30. 40 and 70 to receive, possess and use in amounts as required any byproduct. source or special nuclear material without restriction to chemical or physical form, for sample and analysis, testing, instruent calibration, or associated with radioactive apparatus or components; (4)
GPU Nuclear Corporation, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
c.
This license shall be deemed to contain and is subject to the conditions specified in the following Consission regulations 10 CFR Chapter I: Part 20. Section 30.34 of Part 30. Section 40.41 of Part
- 40. Section 50.54 and 50.59 of Part 50. and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Coeurission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level GPU Nuclear Corporation is authorized to operate the facility at megawatts thermal.gr core power levels not in excess of 2535 steady state react (2) Technical Specifications The Technical Specifications contained in Appendix A. as revised through Asamdsent No.103 are hereby incorporated in the license. The GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
'See Note 1.
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- (3) 2.C(3)
Phys'1 cal Protection The licenses shall fully taplement sind maintain in effect all provisions of the following Commission approved documents, including amendments and changes consist of information withheld from public disclosure pursuant to 10 CFR 2.790(d):
"Three Mile Island Nuclear Station, Unit 1 modified Amended Physical a.
Security Plan", dated February 1, 1978, with Revisions Nos. 1-6 dated Joe 15. July 25, October 27 and November 17, 1978, and January 22 and February 22, 1979, respectively.
b.
"Three Mile Island Nuclear Station, Unit 1 Safegua.rds Contingency Flan", dated February 22, 1980, as revised May 15, 1980, submitted pursuant to 10 CFR 73.40. The Contingency Plan shall be funy implemented, in accordance with 10 CFR 73.40(b), within 30 days of this approval by the Commission.
"Thrsa Mile Island Nuclear Station, Unit 1 Guard Training and Qualifi-c.
cation Plan" dates August 15, 1979 as revised December 19, 1980. This Plan shan be fonowed in accordance with 10 CFR 73.55(b)(4), 60 days after approval by the Commission. All security personnel, as required by the above plans, shan be qualified within two yearsaf this approval.
The licensee may make changes to this plan without prior Commission approval if changes do not decrease the safeguards effectiveness of the plan. The licenses shan maintain records of and submit reports concerning such changes in the same manner as required for changes O
made to the Safeguards Contingency Plan pursuant to 10 CFR 50.54(p).
(4)
The Licenses may proceed with and is requirsd to complete the modifications identified in Paragraphs 3.1.1 through 3.1.23 of the KRC's Fire Protection Safety Evaluation (SE) on the facility dated September 19, 1978 and supple-monts thereto.
These modifications shall be completed as specified in Table 3.1 of the SI or supplements thereto.
In addition, the Licenses shall submit the additional information identified in Table 3.2 of this SE in acccrdance with the schedule contained therein.
In the event these dates for subnittal cannot be met, the Licenses shan submit a report, explaining the circunstances, together vith a revised schedule.
(5) The Licensee shan implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shan include:
a.
Identification of a sampling schedule for the critical parameters and control points for these parameters; b.
Identification of the procedures used to measure the values of the critical parameters; c.
Identification of process sampling points; d.
Procedure for the recording and management of data; 11-2-81
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Pseendeses defiadag acessendes entiens of off seawd poing han[,
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A pseendsse $demeMring n) she===May zeepenethle for the Assesyre-tasian ei the does, and (2) the sequessa and adstag of adsdaistrative t
i aveste seguised to tattiass setzestive settaa.
(6) Insenics Testina 1.
The Ifeensee may proceed with and is required to isolement the Insenice Testin 10 CFR 50.55(a) g program which satisfies the requirements of in accordance with the supporting staff Safety Evaluation dated 2.
The licensee may proceed with and is required to complete the Am.71 modificattens necessitated by the Insenica Testing Progres.
3.
The Ifeensee shall propose alternatives to inservice tests, with appropriate justification for each of the items listed in Table 2.2 of the supporting staff Safety Evaluetten dated August 3.1981, by the dates indicated in Table 2.2.
- 7) Aircraft Movements 5taty (80) days following the report en aircraft movements at the Harrisburg International Airport for the calender year 1984 pursuant to Technical Specification 8.g.1.8.2.b. a report shall be submitted updating tne aircrash probability analysis pro-sented by Metropolitan Edison Cassegg to the Atomic Safety and Licensing Appeal Board in the Ihree mle Island. Unit No. 2 eseration license proceeding (Decket No. 50-320). Such report shall utilias current data en aircraft novaments at the Harris-berg International Airport and gdated national aerial crash rates and shall be based en the same methodelegy presented by hn*8'~
Me 11 tan Edison.Cogeny as accepted by the Appeal Beard in t
Fellowing receipt of such report letC will, after l
discussion with WU Nuclear Corporation, determine the need for further periodic a*rcrash probability analyses.
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Pag 3 66
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Resaired.11assGeneraters In order to confire the leak-tight integrity of the Reacter Coelant tem. including the steen generators, operation of the facility 11 he in accordance with the following:
- 1. Prior to initial criticality, spu IInclear Corporation shall submit to IEic the results of the steem generator het test program and a seemory of its management review.
- 2. GPU IInclear Corporation shall confire the baseline primary-to-secondary leakage rate established during the steen generator hot test progras. If leakage exceeds the baseline leakage rate by more then 0.1 GPII. the facility shall be shot down and leek tested. If any increased leakage above baseline is due to defects in the tube freespan.theleakingtube(s)shallberemovedfromservice. The teseline leakage shall be reestablished. provided that the leakage i
limit of Technical Specification 3.1.6.3 is not onceeded.
- 3. GPU IInclear Corporation shall complete its post-critical test program ateachpeuerrange(0-55.55-505,505-1005) in confermance with the hs.103 program described in Topical Report 000, llev. 3. and shall have available the results of that test program and a stemory of its management review, prior to ascension from each pouer range and prior O
to norme1 peuer operation.
- 4. GPU lluclear Corporation shall conduct edQ-current examinettons, consistent with the extended inservice inspection plan defined in Tabit. 3.31 of IIURES-1019. either 90 calender days after reaching full power, or 120 calender days after ascending 505 peuer operation, whichever comes first. In the event of plant operation for an estended perted at less then 905 peser. SpU IIsclear Corporation shall provide an assessment at the end of ISO days of operation at peuer levels between 55 and 505. such assessment to contain recommendations and supporting information as to the necessity of a special edb-current testing (ECT) shutdeun before the end of the refueling (The IRC staff will evaluate that assessment and detairwine the cycle.
time of the nest ed provisions of the l@ cense conditions.)-current osamination, coasistent with th i
In the absence of such an assessment a special ECT shetdeun shall take place before an additional 30 days of operation at pouer above 55.
- 5. GPU lleclear Corporation shall provide routine reporting of the 1
long-tere corresten " lead tests" test results en a quarterly basis as well es mers timely notification if adverse corresten test tesults are discovered.
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. -. F883 7 This lica c e is effective as of the date of issuance and shall aspire at Eidnight. May 18, 2008.
3 FM TEE ATC911C EERCT CthetIsg5m 1
Original Signed by A. Ciambusso l
A. Cisabusso, Deputy Director for Raastor Projects i
Directorate of :.icensing i
Attachment:
Appendicas A and 3 Technical Specifications Date of Issuance: April 19, 1974 l
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ATTACENT TO LICENSE AMENOMDIT NO.103 FACILITY OPERATING LICENSE N0. OPR-50 DOCKET NO. 50-289 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas.of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3-100 3-100 3-101 3-101 3-102 3-102 3-103 3-103 3-104 3-104 3-105a 3-105a 4-81 4-81 i O I
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EAD10 ACTIVE GA33005 PROCESS AED EFFLUENT WWITORIM ISSTERENTATIOr LIM 1715 00 BIT 105~ 70R OfERATIM s
3.21.2 Se radioactive gaseous process and effisent assitoring instrusestation chamaels shows la Table 3.21-2 shall be OPERAE.E with their Alata/ Trip setpoints set to masse that the limits of specification 3.22.2.1 are not easeeded.
The Alare/ Trip setpoints of these shamaels aball be determined is asserdance with the CDCM.
AFFLICABILITY: As shows la Table 3.21-2 ACTION:
a.
With a radioactive gaseous process or effluent monitoring instrumenta-tion chamael alarm trip setpoint less conservative than required by the l
above, immediately suspend the release of radioactive affluents nomi-tored by affected oh,ammel or declare the chamael inoperable.
b.
With leee thas the simiasm seaber of rediosctire saseemo proceae or effluent osaltoring instrumentation channels operable, take the ACTIOR shown la Table 3.21-2.
BASES The radioactive gaseous effluent instrusestation is provided to monitor O
and control, as applicable, the releases of radioactive materials in gaseous affluents during actual or potential releases. Se alare/ trip setpoints for these instrummats shall be calculated in accordance with NRC l
approved methods la the CDCM to ensure that the alare/ trip will occur pelor to, exceeding the limits of 10 CFE Part 20.
The low range condenser offgas noble gas activity monitors also provide data for determination of steam generator primary to secondary leakage rate. Channel operability requirements are based on an ASLB Order dated -
October 31, 1984.
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Ilote 1: per one of the channels, an operable channel may be deddftr purposes of this specificatten and 4.21.2 only as a suitable equivalent monitoring system f.apable of being placed in service within one hour. A suitable equivalent system shall include instrumentatten with canyarable sonsttivity and response time to the IM-A5Lo monitoring channel. When the equivalent Y
menttering system is in service. Indication wt11 be continuously available to the operator. -
either tW indication and alarm in the control room or through communicatten with a j
j designated individual continuously observing local indication.
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TABIS 3.21-2 (Contiamed) l
' TABLE EDTATICB
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'd.
Prior to degas operations, a grab sample shall be taken and analysed. If the hydrogen concentrattaa is greater than II, nitrogen shall be added to reduce the hydrogen concentrations to less than 12. During the degas operation, a grab sample shall be taken and analysed every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Fellowing the initial makeup tank dis-charge, take and analyse a grab sample for hydrogen, if the byhogen concentration is greater than 1.0%,
nitrogen shall be added to reduce the hydrogen con-centration to less than 1.01.
- If the hydrogen monitor is operational, hydrogen monitor results may be meed rather than grab sample analysis for hydrogen. Alternately, if the oxygen monitor is operational, oxygen monitor results may be used rather than grab sample analysis for onygen.
2.
If the channel is not OPERABLE within seven days, a tele-phone call will be ande by the Vice President of 211-1 (or his designate) to the Director of Engion 1 Office of Inspection and Inforement (or his designate) describing the reasons for the dsley and the corrective actions being O
taken. A written report documenting reasons for the delay and corrective actions taken will be forwarded within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the telephone notification.
ACTION 31 With the ember of channels OPERAEE less than required.by the MinLam Channels OPERABLE requireaant, effinest releases via this pathway may coatisme for ey to 28 days, previded, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> af ter the chamael has been destared Leoperable, saples are continesesty collected with ausiliary sampling equipment.
ACTION 32 With the number of channels 0PERABLE less than required by the minimum channels OPERABLE requirements, affluent releases via this pathway may continue for up to 28 days, provided that one OPERABLE channel remains in service or is placed in service within one hour. After 28 days, or if one OPERABLE channel d;,es not remain in service or is not placed in service within one hour, the provisions of 3.0.1 apply.
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b.
The' steam generater shall be determined 0FEIABLE after complettag the ca..gr'i== actions (removal from servise by plugging, or repair by the kisatic expansion procesa6 sf all tubes exceeding the repair limit and all l
tubes saataistas the-- F cracks) required by Table 4.19.2.
4.19.5 jaggggg, -
a.
Falisetag the completion of each inservice inspection of steam generator tubes, the number of tubes repaired or remrved from service in each steam generator shall be
. g ad to the ERC withia 15 days.
b.
The.eamplete rammits of the steam sensrator tube taservisa taspectism shall be reportad to the ERC withia 3 months fallsstag -
r1=*4= of the taspection. This report aball insinde:
1.
Number and antant of tubes laspectad.
, 2.
Issattom and pareant of well-*h4ah==== penetration for each indicatian of an imperfect 1as.
3.
TAmmetf4matism of tubes resa'ifed or removed from service.
c.
Basults of stamm smaarator tube inspectimas which fall into Catagery C-3 and require prompt notiffe=edan of the ERC aball be report.M pursumma to Specifissaism 6.9.2 prior to resumiptism of plans operattaa. The written fo11 sump of this report shall yesvide a desertymisa of invasedg=e4==
h as dessemias samme of the tube degradatism and astressive measures takaa as peuvent recurramca.
3AEM.
The Surveillanas Esquiramanas ist taspectima of the stamm gemarator tubes ensure that the strussmaal tasagrisy of this paretam of the BCS ggl1 be madmendmad_
4=41 Amendemat No. 47, N,103
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