ML20082U369

Application for Amend to License DPR-16,consisting of Tech Spec Change Request 118 for Clarity & Format Purposes Only. Certificate of Svc Encl

ML20082U369
Person / Time
Site:	Oyster Creek
Issue date:	12/08/1983
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20082U361	List: ML20082U359 ML20082U369 ML20082U377
References
NUDOCS 8312160319
Download: ML20082U369 (15)

Text

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OYSTER CREEK NUCLEAR GENERATIflG STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 118 DOCKET NO. 50-219 Applicant submits by this Technical Specification Change Request No.118 to the Oyster Creek Nuclear Generating Station Technical Specifications, a renovated copy of Appendix A for reissuance.

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By W3 F. B. Fiedler Vice President and Director Oyster Creek Sworn and subscribed to before me this R day of D e , 1983.

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MICHAEL LACGART NOTARY PUBLIC 0F tiEW JERSEY My Commoon Dperes twenber 31.1905 B312160319 831208 PDR ADOCK 05000219 p PDR ._ -

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i UNITED STATES OF A!! ERICA NUCLEAR REGULATORY C0ft!!ISSION IN THE MATTER OF )

GPU !!UCLEAR CORPORATION )

CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No.

118 for the Oyster Creek Nuclear Generating Station Technical Specifications, filed with the United States Nuclear Regulatory Commission on December 8, 1983, has this day of December 9, 1983 been served on the Itayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:

Mayor of Lacey Township 818 West Lacey Road Forked River, N.J. 08731

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-w P. B. Fiedler Vice President and Director Oyster Creek

GPU Nuclear Corporation EE ys 100 interpace Parkway ,

J Mw a Parsippany, New Jersey 07054 201 263 6500 ,

TELEX 136-482 l Writer's Direct Dial Number; December 9, 1983 l

Mayor of Lacey Township 818 West Lacey Road Forked River, N.J. 08731

Dear Mayor:

Enclosed herewith is one copy of Technical Specification Change h quest No.118 for the Oyster Creek Nuclear Generating Station Operating License.

This document was filed with the United States Nuclear Regulatory Commission on Deceder 8, 1983.

Very truly yours, P. dier

/kQ Vice President and Director Oyster Creek 1r l

GPU Nuclear Corporation is a subsidiary of the General Public Utihties Corporation

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i OYSTER CREEK NUCLEAR GENERATING STATION (DOCKET NO. 50-219)

PROVISIONAL OPERATING LICENSE NO. DPR-16 Applicant hereby requests the Commission to reissue Appendix A to the above captioned license..

1 Section to be changed:

Non-technical changes indicated below are applicable to Appendix A in its entirety.

2. Extent of change:

a) Figure and Table designations. changed to be consistent throughout document.

b) Lists of tables and figures provided in " Table of Contents".

c) Scientific notation designation of existing Appendix A Section 3.6 expanded to entire document.

d) Gramatical corrections.

e) Elimination of errors that have developed since the initial issuance of Appendix A.

3. Changes requested:

As indicated on pages 1.1-4, 2.1-1, 2.1-4, 2.3-4,-2.3-5,"3.1-4, 3.1-5,.

3.1-6, 3.2-1, 3.2-3, 3.2-7, 3.3-2, 3.4-2, 3.4-3.-3.4-6, 3.4-7, 3.5-3, 3.5-5, 3.5-6, 3.5-8, 3.5-9, 4.2-1, 4.3-1, 4.5-4,-4.5-7-and 4.5-9.,

with the exception of those generic changes noted in a, b & c above.

4. Discussion:

The renovated copy of Appendix-A of the Oyster Creek Nuclear.

Generating Station Technical Specification is being submitted for clarification purposes and the convenience of the Nuclear Regulatory ')

Commission. No technical changes have been made to the document. 1 Acceptance and issuance of the enclosed Appendix A will provide the l clarification sought by the NRC and will facilitate' future changes.

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OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE ~NO. DPR-16 DOCKET N0. 50-219 i

TECHNICAL SPECIFICATION CHANGE REQUEST NO. 118 Pursuant to 10CFR50.91, an analysis concerning significant hazards considerations is provided below:

1. Section to be changed:

Non-technical changes indicated below are applicable to Appendix A in its entirety.

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2. Extent of change:

a) Figure and Table designations changed to be consistent throughout document, for example Figure 3.10-1 has been changed to Figure 3.10.1 l while Table 3.6-2 has been char.ged to Table 3.6.2

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b) List of tables and figures provided in " Table of Contents".

c) Scientific notation designation ~ of existing, Appendix A Section 3.6 expanded to entire document, for example 61x10 on page 2.3-1 has been changed to 61.0E6.

i d) Grammatical corrections, for example "that" has been changed to "than" in specification 3.4.C.2..

e) Elimination of errors that have developed since the initial issuance of Appendix A, for example the statement "Any four rod groups may contain a control rod which is" appears on both page 3.2-la and i 3.2-2. The statement has been eliminated from page 3.2-la.

3. Discussion:

Examples of amendments that are considered not likely to involve significant hazards considerations were provided in the Federal Register on April 6, 1983 (48 FR 14870). Reissuance of Appendix A'of the Oyster Creek Technical Specification is within the provisions of example (i) (as referenced above) in that it is purely an administrative change. The renovated copy of Appendix A is being provided for clarification purposes and the convenience of-the NRC.

The administrative changes are being made to achieve consistency I throughout the document and to eliminate errors that have _

j~ inadvertently developed-since its initial issuance.- .No technical _-

changes have been made to the document. Acceptance and issuance of the enclosed document will provide the clarification sought by the commission and will. facilitate future changes.

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4. Determination:

We have determined that the subject change request involves no significant hazards in that operation of the Oyster Creek Nuclear Generating Station in accordance with Technical Specification Change Request No. 118 would not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or-

2) Create the possibility of a new or different kind of accident from any previously evaluated; or

3) Involve a significant reduction in a margin of safety.

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RECORD OF CHANGES CHAf'GE NO DATE OF CHAf!GE PURPOSE OF CHAMGE Errata (Er.) April 9, 1969 Correct errers and omissions in l n)

(\._./ Attachment A initial printing l to Amendment No 1 August 1, 1969 Miscellaneous changes issued when power level of 1600 MWt authorized 1 November 13, 1969 Rev. fuel clad integrity safety limit 2 January 5, 1971 Allow bypassing of rod block functions during startup 3 February 8, 1972 Permits surveillance of instruments and trip systems without tripping protection system channel.

4 October 16, 1970 Miscellaneous changes required to permit primary containment leakage rate testing.

5 December 2, 1970 Changes associated with power level uprating to 1690 MWt.

6 March 18, 1971 Allows use of TIP for malfunctioning LPRM under certain circumstances.

7 November 5, 1971 Changes associated with power level uprating to 1930 MWt. Also updates  ;

in accordance with new Fed Regs 8 October 6, 1971 Allows for LPRM string replacement

< without violating Tech Specs.

9 November 22, 1971 Permits operation on November 23 and 24, 1971 without inerting -

cancelled November 24, 1971 10 March 23, 1972 Increase limit on radioactivity in Haste Storage Tanks to 10.0 curies.

1 11 May 18, 1972 Removes requirement for containment ,

spray system operability when primary containment not required 12 June 12, 1972 Adjusts relief valve and other setpoints to be consistent with transient analysis based on more conservative scram reactivity curve f

13 April 24, 1973 Specifies new loadsetting for -

refueling interlock grapple switch as a result of the' installation of a new & lighter refueling grapple

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14 May 22, 1973 Revises plcnt R3 porting Requiro ments section in its entirety 15 May 25, 1973 Incorporates the XN-1 Critical Heat Flux Ccerelation into the Tech Specs to allow the use of this correlation for the determination of safety limits for cperation 16 August 24, 1973 Specifies a Section 3.10 and 4.10 which place limiting cond.tions of operation and surveillance require-ments on the reactor power distribution by limiting the local and average planar linear heat generation rate.

17 November 16, 1973 Modifies Change 16 by increasing the limit on maximum average planar linear heat generation rate.

16 December 18, 1973 Modifies Change 17 by increasing the limit on MAPLHGR and revising the basis to raflect the appropriate technical references.

19 January 22, 1974 Change allowed operation at 50%

power with the 02 Content of Centain-ment above 5 velume percent for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> between 12:30 on January 22, 1974 and 12:30 pm en January 24, 1974 20 (Amend =ent No 4 June 11, 1974 Technical Specification change to to Facility License DPR-16) accommodate Cycle IV reload fuel.

21 (Amendment No 5) July 5, 1974 Allows operation at 50% power with 02 Content of Containment above 5 volume percent for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from 10:15 pm July 2, 1974 to 10:15 pm July 3, 1974.

22 (Amendment No 6) September 27, 1974 Provides for modifications to the LCO, s.treveillance requirements and bases for the torus to drywell vacuum breakers.

23 (Amendment No 7) February 14, 1975 Permits lowering of MS1V low main steamline pressure closure setpoint.

24 (Amendment No 8) May 24, 1975 Incorporates opersting limits -

into Tech Specs for facility based on an acceptable evaluation model.

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25 (Amendment No 9) May 24, 1975 Authorimes operation with 8x8 fuel assemblics and changes to Tech Specs.

S (Amendment No 10) Issued 1/16/76 Modifies Section 6, Administrative Effective 3/16/76 Controls.

27 (Amendment No 11) December 11, 1975 Mcdifies limits for Suppression Pool water temperature.

Amendment No 12 January 21, 1976 Reduce core spray system capability during modification to ECCS.

) Amendment No 13 February 19, 1976 Affect control rod specifications i for control rod drive mechanism collet housing failure.

i Amendment No 14 March 22, 1976 Modifies the limiting conditions for operation and surveillance requirements for installed filters in standby gas treatment system.

Amendment No 15 February 24, 1976 Revise specifications for MAPLHGR and ADS as result of re-evaluation of ECCS.

, Amendment No 16 July 26, 1976 Revise MCPR safety and operating and revised limits, increase MAPLHGR, and e August 2, 1976 revise certain related surveil-4 lance requirements and remedial actions.

Amendment No 17 November 26, 1976 Revise Section 6, Administrative Controls.

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Amendment No 18 December 30, 1976 Incorporates Limiting Conditions for Operation and Surveillance Requirements for safety related snubbers.

Amendment No 19 January 25, 1977 Provides for the possession and use of special Nuclear Material and incorporates requirements for leak test-ing source material.

Amendment No 20 February 4, 1977 . Permits resetting a reactor scram 20 seconds after the reactor has been placed in the shutdown mode.

Amendment No 21 February 4, 1977. Allows alternate emergency core cooling provisions with-fuel in the vessel and permits Y .

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draining the H ter from thn torus under specified conditions.

Amendment No 22 March 30, 1977 Modifies the spent fuel storage pool to allow high density storage rac!s for storage of up to 1800 fuel assemblies.

Anndment No 23 March 30, 1977 A11ous unloading and reloading the core during the 1977 refueling cutage.

Amendeent No 24 September 19, 1977 Delete limits for Fuel Type I & III. Extend MAPLHGR curies for other types.

Amendment No 25 November 28, 1977 Revision of Administrative Controls to be consistent with standard Tech Specs and editorial corrections.

Amendment No 26 February 14, 1978 Revises Section 6.3.1 relating to the qualification of the Supervisor, Radiation Protection.

Amendment No 27 February 14, 1978 Delete Annual Operating Report.

Amendment No 28 February 22, 1978 Add a definition of Surveillance Requirements.

Amendment No 29 March 3, 1978 Add Tech Specs for fire protection systems and controls.

Amendment No 30 March 14, 1978 Extended MAPLHGR curves.

Amendment No 31 Apri". 19, 1978 Deletion of Section 6.12

" Respiratory Prvtection Program".

Amendment No 32 June 20, 1978 Add drywell to torus differential pressure requirement.

Amendment No 33 November 11, 1978 Revises HAPLHGR and adds a HAPLHGR multiplier.

l Amendment No 34 November 24, 1978 Increased Core Spray l System ISI and increased flow requirement in -

CSS System 2.

Amendment No 35 May 30, 1979 Revises HAPLHGR curve O

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(Figure 3.10-1).

Amendment No 3G May 30, 1979 Extends safety limit of m 4'8" of Hater above core i to all modes of Reactor Operation and adds safety Limit (F) requiring 2 recirculation loop suction discharge valves open.

Amendment No 37 June 6, 1979 Environmental Tech Specs (Apendix B).

Amendment No 38 June 29, 1979 Inclusion of supplements in License Requirement 3.E pertaining to Fire Protection Modifications.

Amendment No 39 July 25, 1979 Add Limiting Safety System Setting &

modifies MAPLHGR curve.

Amendment No 40 August 6, 1979 Modify administration controls concerning supervision of refueling and facility organization.

Amendment No 41 September 14, 1979 To incorporate the Security Plan into the Operating License.

A Amendment No 42 October'16, 1979 Revise NDT Pressure Temperature Q limits.

Amendment No 43 January 4, 1980 Unioading and reloading core Hithout use of blade guides;

- allow single and multiple control

rod drive maintenance.

Amendment No 44 January 4, 1980 Modify definitions'of shutdown and refueling conditions;~ elimi-nates unnecessary operability and surveillance requirements.

Amendment No 45 January 25, 1980 Revise draining requirements for the torus.

Amendment No 46~ April 23. 1980 Revise drywell to torus-I differential pressure.

Amendment No 47 . Hay 15, 1980 Replacement of core spray spargers.

-Amendment No 48 . June 2,^1980  :

MAPLHGR limits and multiplier -

for five and four recirculation loop operation.

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Amendment No 49 August 20, 1980 Incorporats gis:cus d; sign objectives of 10 CFR 50 Appendix I as Limiting Conditions for Operation.

Amendment No 50 September 15, 1980 Revises Section 6 to reflect the establishment of the GPU Nuclear Group.

Amendment No 51 September 25, 1980 Authorizes implementation of Safeguards Contingency Plan.

NRC Order October 24, 1980 Records for Environmental Qualification.

Amendment No 52 February 11, 1981 Allcus SGTS methyl iodine removal efficiency to be determined in accordance Hith ASTM D 3803-79.

Amendment No 53 February 11, 1981 To incorporate the Guard Training and Cualification Plan into the Operating License.

NRC Order April 20, 1981 Primary coolant system pressure isolation valves.

Amendment No 54 May 8, 1981 Addresses TMILL requirements as follows: containment isolation valves, shift technical advisce, relief and safety valve position indicators, program concern-ing the integrity of systems outside containment and a program concerning iodine monitoring.

Amendment No 55 August 13, 1981 Incorporates 125 VDC distributien system modification and requires surveillance of the station batteries to reflect IEEE STD. 450.

Amendment No 56 September 2, 1981 Deletes various studies and monitoring requirements in Appendix B.

Amendment No 57 November 25, 1981 Modifies requirements of Safety & Relief Valve -

poisiten indication instruments.

Amendment No 58 December 21, 1981 Authorizes changes for O

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edditional fire protection systems that were installed during the 1980 refueling outage.

4 Amendment No 59 January 1, 1982 GPU Nuclear Corporation.

) Amendment No 60 February 3, 1982 Addresses diesel generator loading and surveillance j requirements.

Amendment No 61 June 11, 1982 Authorized a one time only change to Section 1.12, Definition of Refueling Outage, to extend the time between successive tests of surveillances, price to

cycle 10 only, from not exceeding 20 months to not exceeding 30 months.

i Amendment NO 62 July 12, 1982 Authorized changes to the limiting setpoints for five electomatic relief valves for the Reactor Coolant i System.

Amendment No 63 October 15, 1982 Incorporates the rod block functions associated with SDV high Hater level and scram trip bypass.

Amendment No 64 October 28, 1982 Clarify the term " OPERABLE" as it applies to support system outages or multiple outages of redundant components.

Amendment No 65 November 5, 1982 Revises Oyster Creek Administration by retitling-position of Director

-Station Operations to Deputy Director Oyster Creek and sharing his Tech Spec responsibilities-with the Vice President and Director Dyster Creek.

Amendment No 66 Herch 24, 1983 Deletion of water quality limits and monitoring programs from Appendix B.

Amendment No 67 March 31, 1983 Ups the auditing -

frequency of the Emergency and Security Plans to every 12 months.

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Acend ent No 68 September 28, 1983 Revises the plant organi=ation. Retitles several positions and transfers corrective maintenance to M&C.

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