ML20140F835

Amend 114 to License DPR-50,changing Tech Spec to Authorize Operation at Steady State Reactor Core Power Levels Not to Exceed 2,535 Mwt

ML20140F835
Person / Time
Site:	Three Mile Island
Issue date:	03/14/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:
References
NUDOCS 8604010189
Download: ML20140F835 (9)

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UNITED STATES 8 g NUCLEAR REGULATORY COMMISSION o j w AsHINGTON. D. C. 20555

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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET N0. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 114 License No. OPR-50

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by GPU Nuclear Corporation, et al.

n (the licensees) dated October 24, 1985, as supplemented Decenber 10,

! ) 1985, complies with the standards and requirenents of the Atomic

'"' Energy Act of 1954, as amended (the Act), and the Comission'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 Conmission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conductea 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 reouirements have been satisfied.

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. DPR-50 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. ll4 , are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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~ 'Jo n F. Stolz, Directo P Project Directorate #6 ivision of PWR Licensing-B 4

Attachment:

Changes to the Technical Specifications

• Date of Issuance: March 14,1986 l

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(3) GPU Nuclear Corporation, pursuant to che Act and 10 CFR Parts 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 analysis, testing, instrument 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 Commission 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 pro ~ visions of the Act and to the rules, regulations, and orders of the Commission 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

.l'~'T steady state reactor core power levels not in excess of 2535 V megawatts thermal.4 (2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 114 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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4 PAGE 1 of 4 TMI-1 TECHNICAL SPECIFICATIONS q

') APPENDIX A TABLE.0F EFFECTIVE PAGES PAGE REY. PAGE REV.

1 72 3-10 11 98 3-11 iii 108 3-12 47 iv 97 3-13 4-20-81 y 77 3-13a 4-20-81 vi 106 3-14 vii 109 3-15 17 viii 77 3-15a 4-20-81 3-16 45 1-1 3-17 1-2 93 3-18 1-3 3-18a 1-4 3-18b 42 1-5 36 3-18c 78 1-6 72 3-18d 78 1-6a 72 3-18e Deleted 1-7 72 3-18f 97 1-8 72 3-18g 97 Fig. 3.1-3 2-1 17 3-19 98 2-2 90 3-20 50 l 2-3 50 3-21 98 2-4 78 3-22 98 Fig. 2.1-1 50 3-23 Fig. 2.1-2 50 3-24 80 Fig. 2.1-3 50 3-25 98 2-5 28 3-26 78 2-6 50 3-26a 78 2-7 78 3-27 98-2-8 78 3-28 78 2-9 90 3-29 78 Fig. 2.3-1 78 3-30 114 Fig. 2.3-2 50 3-31 78 3-32 78 3-1 98 3-32a 78 3-la 98 3-33 17 3-2 47 3-34 90 3-3 29 3-34a 50 3-4 29 3-35 50 Fig. 3.1-1 29 3-35a 50 Fig. 3.1-2 29 3-36 50 3-5 29 3-36a 39 3-6 78 Fig. 3.5-2A 50 3-6a 78 Fig. 3.5-28 50 3-7 78 Fig. 3.5-2C 50 3-8 108 Fig.' 3.5-2D 50 3-9 108 Fig. 3.5-2E 50 3-9a 108 Fig. 3.5-2F Deleted 0 3-9b 108 Revision 0 unless otherwise indicated.

Amendment No. 114

e PAGE 2 of 4 s /'"'s PAGE REY. PAGE REY.

('~') Fig. 3.5-2G 90 3-82 to 3-85 Blank Fig. 3.5-2H -50 3-86 101 1 3-37 89 3-87 111 1 3-37a 89 3-87a 111 l 3- 38 3-88 32 l 3-39 3-89 101 3-40 3-90 101 l 3-40a 100 3-91 101 ,

3-40b 100 3-92 101 3-40c 105 3-93 101 3-40d 3-94 101 3-40e 100 3-95 59 Fig. 3.5-1 3-95a 81 Fig. 3.5-2 3-95b 81 Fig. 3.5-3 3-95c 81 3-41 108 3-96 88 3-41a 108 3-97 88 3-41b 108 3-98 72 3-41c 108 3-99 88 3-42 3-100 103 3-43 98 3-101 104

3-44 27 3-102 103 3-45 3-103 103 3-46 64 3-104 103 3-47 to 3-54 Deleted 3-105 104 0 3-55 3-56 3-56a 109 109 109 3-105a 3-106 3-107 104 72 72 3-56b 109 3-108 72 3-57 3-109 72 3-58 3-110 72 3-59 3-111 72 3-60 3-112 72 3-61 76 3-113 72 3-62 55 3-114 72 3-62a 108 3-115 72 3-62b 108 3-116 104 3-62c 76 3-117 72 62d 55 3-118 72 3-63 106 3-119 72 3-64 106 3-120 72 3-65/66 Deleted 94 3-121 72 3-67/68 61 3-122 72 3-69 94 3-123 72 3-70 30 3-124 72 3-71 61 3-125 72 3-72 to 78 30 3-126 72 3-79 61 3-127 72 3-80 75 3-81 41 O

G Amendment No.114 o

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4-1 100 4-52 78 4-2 78 4-52a 78 4-2a 78 4-52b 78 4-3 102 4-53 4-4 47 4-54 97 4-5 78 4-55 68 4-Sa 108 4-55a 55 4-6** 24 4-55b 108 4-7 80 4-55c 108 4-7a 105 4-55d 76 4-8 78- 4-55e 55 4-9 108 4-56 64 4-10 108 4-57 Blank 4-10a 100 4-58 4-11 71 4-59 65 4-12 11-2-81 4-60 110 4-12a 11-2-81 4-61 110 4-13 60 4-62 106 4-14 to 4-27 Blank 4-63 106 Fig. 4.2-1 Deleted 4-64 110 4-27a 60 4-65 106 4-28 4-66 110 4-29 63 4-67 to 4-71 Blank 4-30 27 4-72 101 4-31 63 4-73 32 O 4-32 4-33 4-34 93 93 113 4-73a 4-73b 4-73c 32 32 32 4-34a 113 4-74 32 4-34b 113 4-75 101 4-34c 113 4-76 108 4-35 95 4-76a 101 4-35a 59 4-77 47 4-36 59 4-78 47 4-37 108 4-79 47 4-38 108 4-80 86 4-38a 87 4-81 103 4-39 78 4-82 86  !

4-40 70 4-83 47 l 4-41 68 4-84 47 i 4-42 68 4-85 86 )

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4-86 47 l 4-44 68 4-87 72 i 4-45 4-88 88 4-46 70 4-89 72 4-47 78 4-90 72 4-48 4-91 104 4-49 4-92 72 4-50 4-93 72 4-51 95 Amendment No. 114

PAGE 4 of 4 4 PAGE REV. PAGE REY.

4-94 72 6-1 77 4-95 72 6-2 77 4-96 72 6-3 92 4-97 72 6-4 77 4-98 72 6-5 77 4-99 88 6-6 77 4-100 72 6-7 84 4-101 72 6-8 99 4-102 72 6-9 99 4-103 72 6-10 77 4-104 72 6-11 84 4-105 72 6-12 77 4-106 72 6-13 82 4-107 72 6-14 77 4-108 72 6-15 77 4-109 72 6-16 - 77

'4-110 72 6-17 108 4-111 72 6-18 77 4-112 72 6-19 77 4-113 72 6-20 77 4-114 72 6-21 107 4-115 '

72 6-22 102 4-116 72 6-23 102 4-117 72 6-24 77 4-118 72 Fig. 6-1 92 O 4-119 4-120 4-121 72

.72 72 Fig. 6-2 112 4-122 72 Fig. 4.17-1 .106 5-1 72 Fig. 5-1 72 Fig. 5-2 72 Fig. 5-3 72 5-2 5-3 5-4 5-5 5-6 5-7 34 5-8 1-20-76 5-9 1-20-76 5-10 72 Fig. 5-4 72 5-11 72

• • Amendment Number Missing

( Amendment No.114

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y Table 3.5-1 Cintinued g .*

INSTRtMENTS OPERATILG CONDITIONS 4  %

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. (A) (B) (C) g Functional Unit Mininum Operable Minimum Degree Operator Action if Conditions l of Redundancy of Column A and B Cannot be Met

. Cha nnel s M

- A. Reactor Protection System (Cont'd.)

2 Maintain hot shutdown

• 9. Power / nuder of pugs 2 1 instrument channels

10. High reactor building 2 1 Maintain hot shutdown pressure channels (a) For channel testing, calibration, or mintenance, the minium nuder of operable channels my be two and a degree of redundancy of one for a eximm of four hours.

(b) Whc.,7 of 4 power range instrument channels are greater than 10 percent full pow =r, hot shutdown is not required.

w (c) When 1 of 2 intermediate range instrument channels is greater than 10-10 ags, or 2 of 4 power range instrument

. L, channels are greater than 10 percent full power, hot shutdown is not required.

, o B. Other Reactor Trips

1. Loss of Feedwater 2(a)(c) 1(a)(c) Maintain less than 75 indicated reactor power.

! 2. Turbine Trip 2(b)(c) 1(b)(c) Maintain less than 20% indicated reactor power.

(a) Bypass of the feedwater pump trip signal say be placed in effect when indicated reactor power is less than 7%.

The bypass will be removed when reactor power is raised above 71.

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! (b) The main turbine trip bypass say be placed in effect when indicated reactor power is less than 205. The bypass

! will be removed when reactor power is raised above 20%.

I (c) Trip say be defeated during low power physics tests.

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UNIT 1 LICENSE / TECH. SPEC. CHANGE INSTRUCTION MEMO CORRECT ADDRESS .

IF NECESSARY u. s. Nuctena acG. connisS1oN LICENSING DEPARTMENT RETURN TO: Betty Nash WSHINGTON, DC 20555

~. Procedure Distribution Control u 37 Unit 2 Admin. Bldg.

Date 9 R '7-H Please todate your Unit 1 Technical Specifications with the attachments as instructed below. Also, please sign the acknowledgient at the bottom of this memo and return to Betty Ncsh at the address shown above.

] License Ammendment Nunber 114 _ Order for Modification of License Remove Insert Appendix Section Pace No. Amendment Page No. Amendment A t.ic en s e 1.2&5 113 1. 2 & 5 114 Table of Effective Pages 1.2.3.4 113 1.2.3.4 114 A 3 3-30 78 3-30 114 ADDITIONAL INSTRUCTIONS /COHvENTS Amendment 114 was issued 3-14-86 and received 3-25-86 in response to Change Request No.141 and becomes effective as of the date of its issuance (3-14-86).

I hereby acknowledge receipt of the items above ve con ed with the instructions. J 8 hf 0

(Signature) (Ext. N . (Date) 0Do A0000482 6-81

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