ML20064N413

Application to Amend License DPR-16 Consisting of Tech Spec Change Request 96,incorporating Cycle 10 Limits for Operation & Future Cycles Determined by Methods Described in NEDO-24195

ML20064N413
Person / Time
Site:	Oyster Creek
Issue date:	08/31/1982
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20064N395	List: ML20064N392 ML20064N413 ML20064N448
References
NUDOCS 8209080350
Download: ML20064N413 (13)

Text

_

GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 Technical Specification Change Request No. 96 Docket No. 50-219 Applicant submits, by this Technical Specification Change Request No. 96 to the Oyster Creek Nuclear Generating Station Technical Specifications, a change to Specifications listed on Attachment No. 1, the Summary of Technical Specification change request.

By:

Vice Tresident and Director, Oyster Creek 8/ day of gocg[1982.

Sworn and subscribed to before me this

.. g Wb nu Y i

Notary Public f/d 8209080350 820031 PDR ADOCK 05000219 PDR p

UNITED STATES OF AMERICA NUCLEAR REGULATORY CO?NISSION IN THE MATTER OF

)

)

DOCKET SIMBER 50-219 GPU NUCLEAR CORPORATION

)

CERTIFICATION OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 96 for the Oyster Creek Nuclear Generating Station Technical Specification, filed with the U. S. Nuclear Regulatory Commission on August 31,1982 has this 31 day of August been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail addressed as follows:

The Honorable Theodore Hutler Mayor of Lacey Township 818 W. Lacey Road Forked River, NJ 08731 ei By:

Vice President and Director - Oyster Creek DATED:

August 31, 1982

=

GPU Nuclear m

a

'oo 'ote'= ace Par 5way

- 1

-- Umear Pars.ccany. New Jersey 07054 201 263-6500 TELEX 136-482 Writer s Direct D ai Numcer August 31, 1982 The lionorable Theodore liutler Mayor of Lacey Township 818 W.

Lacey Road Forked River, NJ 08731

Dear Mayor liutler:

Enclosed herewith is one copy of Technical Specificiation Change Request No. 96 for the Oyster Creek Nuclear Generating Station Technical Specifications.

These documents were filed with the U. S. Nuclear Regulatory Commission on August 31, 1982.

Very truly yours, P. B.

riedler Vice President and Director - Oyster Creek blf Enclosure i

l

(

GPU Nuclear is a part of the General Puche Utiht es Sys:em 1

I i

P GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE DPR-16 (DOCKET No. 50-219)

TECHNICAL SPECIFICATION CHANGE REQUEST NO. 96 Applicant hereby requests the Commission to change 'he Technical Specifications (Appendix A of the above captioned license) as fo11c ws:

1.

Sections to be Changed Section Description of Changes 1

Add page 1.0-6 2.1 Replace entire section 2.2 Replace entire section 2.3 Replace entire section 3.1 Replace pages 3.1-11, 12 and 12a only 3.2 Replace entire section 3.4 Replace entire section 3.5 Replace pages 3.5-4a through 3.5-7 only 3.10 Replace entire section 4.2 Replace entire section 4.10 Replace entire section j

i l

Extent of Change To incorporate limits determined by methods described in NEDO-24195 and current FDSAR including all applicable amendments into Appendix A,

Technical Specifications and Bases to Provisional Operating License DPR-16, Oyster Creek Nuclear Generating Station.

(See enclosed Attachment No. 1).

Changes Reauested j

See enclosed Attachment No. 2 m.,,

2-Discussion The enclosed Attachment No. I presents a summary of proposed changes by indicating af fected sections and pages of the current specifications, extent of changes and justifications for changes.

There are three categories of changes:

editorial and repaging, deletion of obsolete and non-applicable bases statements, and those due to changes in methods, fuel design and fuel vendor.

Editorial changes and repaging have been proposed in such a manner that no technical meaning has been changed.

Vertical bars have been placed at affected sections where extensive changes are made in Attachment No. 2.

Several obsolete and non-applicable bases statements, discussing initial core and methods have been deleted.

These sections have been identified in Attschment No. 2.

Those limits changed due to changes in methods, fuel design and fuel vendor have been identified in Attachments No. I and 2.

For convenience, entire sections have been replaced even though only minor changes may be involved.

The reference cycle reload is used to present new nuclear evaluation methods for Oyster Creek reload analysis.

It is not intended to be a submittal for an actual Oyster Creek reload.

The new evaluation methods will be used to analyze both GE and Exxon Nuclear Company, Inc. (ENC) fuel designs.

The previous submittal for nuclear evaluation method s, Amendment 76 to.the FDSAR, will be superceded.

However, those sections of Amendment 76 which pertain to ENC reload fuel design and ECCS analysis, and the fuel operating and design limits associated with those sections will remain applicable.

Technical specification limits for local linear hea t generation rate and average planar linear heat generation rate for ENC f uel designs will be based on ENC analyses previously submitted.

At the time of this submittal, reload core transient analyses by GE's ODYN c om pu t e r code and MAPLHGR limits by GE's ECCS Evaluation Model are not available.

The proposed technical specification changes and appropriate sections of NED0-24195 will be updated when these results become available.

We anticipate these updates will be submitted by December 31, 1982.

~

R Attachment No. 1 Summary of Tecli Spec Change Request I

j Current Proposed Extent of No.

Tech Spec Tech Spec Change Justification I

i 1

Section 1 Definitions i

Definition l

1 page 1.0-6 Add new definition for FLPD, MFl.PD, FRP, and TAF i

Section 2.1 Safety Limit - Fuel Cladding Integrity 2

Specification Specification Use of Safety Limit Curve (Figure 2.1.1)

See Bases Statement, 2.1.A,A.1 and A.2 2.1.A is replaced by MCPR Ll.07 for reactor first two paragraphs l

page 2.1-1 page 2.1-1 pressure d 800 psia and core flow d10%

in page 2.1-2 and specification rated. MCPR limits for type VB fuel is 2.1.E replaced by one limit for all fuel types page 2.1-2 in core.

1 3

Specification Specification Reactor power is limited to 25% rated See Bases Statement, 2.1.B 2.1.B for reactor pressure L 800 psia and third and fourth I

page 2.1-1 page 2.1-1 core flow L10% rated.

paragraphs in page 2.1-2 and extended to page 2.1-3 1

4 Specification Specification Neutron flux scram setting at 1.75 See Bases Statement, 2.1.C 2.1.C seconds is replaced by proposed first paragraph in page 2.1-1 page 2.1-1 specification 2.3.A.1 and A.2 in page 2.1-3 of proposed page 2.3-1.

Tech spec.

i 5

Specification Specification Water level is changed from 4'8" See Bases Statement, 2.1.D 2.1.D to 10" above the TAF second paragraph in page t

{

page 2.1-2 page 2.1-1 2.1-3 and first para-graph in page 2.1-4 6

Bases Statements Bases Statements Entire Bases Statements have been See 2 through 5 above pages 2.1-2 pages 2.1-2 revised in accordance with changes 2 through 5 above, except first paragraph of page 2.1.4a of Current Tech Spec.

I

,i

s 2

t

^

Current Proposed Extent of l

N_o. Tech Spec Tech Spec Changes Justification o

7 References References Replace all references with NEDO-24195, General Electric page 2.1-5 page 2.1-4 NEDO-24195 Reload Fuel Application for Oyster Creek describes de-tails of GE supplied reload f

fuel design and reload methodology to be used for future cycles.

Section 2.2 Safety Limit - Reactor Coolant System Pressure 8

Base Statement Base Statement Delete duplicate bases statements Technical Specification change j

paragraph 5 paragraph I and combined them into one.

request No. 98; NRC approved as Amendment No. 62.

page 2.2-1 page 2.2-2 and paragraph I page 2.2-2 i

9 References References References 2 and 3 are In accordance with changes j

page 2.2-2 page 2.2-2 replaced by NEDO-24195 in Bases Statement as descr-ibed in 8 above.

i

! I Section 2.3 Limiting Safety Systems Settings 4

10 Specification Specification APRM flux scram setting function See Bases Statements, para-2.3.1.a 2.3.A.1 is modified by replacing graphs 3 and 4 of page 2.3-4 entire page 2.3-5, and page 2.3-1 pages 2.3-1 and-2 PFo FRP paragraph 1 of page 2.3-6 PF' MFLPD of proposed Tech Spec.

i 11 Specification Specification Control rod block function is See justification 10 above.

i 2.3.2a 2.3.B modifled'by replacing page 2.3-2 page 2.3-2 PFo by FRP PF MFLPD i

i

i i

3 1

i j

Current Proposed Extent of No.

Tech Spec Tech Spec Changes Justification 12 Specification Specification Two groups of ERV setpoints Technical Specification change j

2.3.4 2.3.D are introduced: 2 values at request No. 98; NRC approved as page 2.3-2 page 2.3-3 1070 psig and 3 values at 1090 Amendment No. 62.

psig.

f i

13 Specification Specification Time delay for Isolation See License Amendment No.39 t

2.3.5 2.3.E Condenser Initiation change l

page 2.3-2 page 2.3-3 from 15 to 3 seconds.

I 14 Bases Statements Bases Statements PFo is replaced by FRP To support changes 10 and 11 paragraph 3 of paragraphs 3 and pF MFLPD page 2.3-3, 4 of page 2.3-4 entire page 2.3-4, entire page 2.3-5 and paragraph I and paragraph 1 of page 2.3-5 of page 2.3-6 Delete obsolete reference to See justification of change 15 Bases Statement in paragraph 2, peak pressure of turbine trip 12 above.

page 2.3-5 without bypass.

I --

Delete obsolete statement See Extent of Change.

16 Bases Statement, In paragraph I reference to void reactivity page 2.3-6 coefficient.

Delete non-applicable statement See Extent of Change.

17 Bases Statements. - ---

reference to scram settings.

paragraph 3 page 2.3-6 and in paragraph 3 page 2.3-7 Delete non-applicable statement See Extent of Change.

18 Bases Statement

?

in paragraph 4 reference to MCHFR.

1 page 2.3-7 19 References References Delete non-applicable references.

See Extent of Change.

pages 2.3-7 and 8 page 2.3-8 J

_=_-

= _. _

1

+

1 Section 3.1 Protective Instrumentation l

I s

i Current Proposed Extent of No.

Tech Spec Tech Spec Changes Justification 20 Table 3.1.1 Table 3.1.1 Minimum operable number of In accordance with Specification Specification Specification SRM is changed 3 to 2 and delete, 3.9.E and F.

K.1 and 2 K.1 and 2 note y in page 3.1-12a.

page 3.1-11 page 3.1-11 l

t and note y, page 3.1-12a.

21 Table 3.1.1 Table 3.11 Permissible pressure. level Range of CETAB as i

Note b Note b change from 600 psig to described in NEDO-24195.

page 3.1.12 page 3.1-12 800 psia.

1 I

Section 3.2 Reactivity Control l

i 22 Specification Specification Design Criteria for rod drop See last paragraph of 3.2.B.2.b 3.2.B.2.b accident of 1.25%

is page 3.2-5 of proposed page 3.2-la page 3.2-2 replaced by 280 cal /gm.

Tech Spec.

23 Specification ; ; ---

Delete Requirement of Control All rod out at end of

~

3.2.B.6 i

rod density of 3.5% during cycle condition is analyzed page 3.2-2 power operation.

and presented in NEDO-24195.

24 Bases Statement Bases Statement Revise statements referencing See Extent of Change.

paragraph 4 paragraph 4 the first cycle core to be l

page 3.2-3 page 3.2-4 consistent with reload fuel and core.

See Justification for Change 22.

i 25 Bases Statement Bases Statements See change 22 above.

paragraphs 2 and 3 paragraph 3 page 3.2-4 page 3.2-5 26 Bases Statement Bases Statement Non-applicable scram reactivity New scram reactivity l

in paragraph 3 in paragraph I curve is deleted.

curve for each reload core will be evaluated.

page 3.2-4 page 3.2-6 t

J i

i

- 5 Current Proposed Extent of Ns. Tech Spec Tech Spec Change Justification 27 Bases Statements Bases Statement Delete obsolete reference to in-See Extent of Change, paragraphs 3 and 4 in paragraph 2 operable control rod patterns.

page 3.2-5 page 3.2-6 28 Bases Statement Delete reference statement for i

See Justification for in paragraph 2 3 SRM.

change 20 above.

page 3.2-6 29 Base Statements Base Statement Statements pertaining to sur-Justification of 7-day paragraphs 2, 3, paragraph 3 veillance requirements for requirement is deleted and 4 standby liquid control system from Tech Spec and attached page 3.2-7 page 3.2-8 pumping circuit have been to a plant operations and paragraphs 1, revised.

procedure.

2, and 3 page 3.2-8 30 Bases Statement

= - - - - - -

Description for 3.5% control Analysis in NEDO-24195 paragraph I rod density is deleted.

includes all rod out at page 3.2-9 end of cycle cases.

31 References References Delete non-applicable See Extent of Change.

page 3.2-9 page 3.2-9 references.

Section 3.4 Emergency Cooling 32 Specification: ! ! Specification Change from 4'8" to 10" See Justification for Change 5.

3.4.A.6 and 7 3.4.A.6 and 7 page 3.4-1 page 3.4-1 Bases statement Bases statement paragraph 1 paragraph 1 4

paragraph 4 page 3.4-4 page 3.4-4 paragraph 1 page 3.4-4a O

I

6 Current Proposed Extent of No.

Tech Spec Tech Spec Change Justification Section 3.5 Containment 33 Bases statement Bases statement Criteria for the worst case See Justification for change 22.

paragraph 2 paragraph 2 rod drop accident limit is page 3.5-4a page 3.5-4a changed from 1.5%k to fuel damage criteria.

Section 3.10 Core Limits 34 Specification Specification Add APLllGR for GE supplied Introduction of GE designed 3.10.A 3.10.A, A.1, reload fuels.

fuel into Oyster Creek core.

page 3.10-1 A.2, and A.3 See NEDO-24195 for detail page 3.10-1 design information.

35 Specification Specification Delete LilGR and AP/p values See Justification for change 34, d

3.10.B 3.10.B, B.1, B.2, for fuel type IIIF and add page 3.10-1 and B.3 LilGR value for GE supplied page 3.10-2 reload fuels.

36 Specification Delete assembly averaged No type IIIF fuel in Oyster Creek 3.10.C power void relationship core.

page 3.10-2 for fuel type IIIF.

Bases statements Delete statements per-paragraphs 4 & 5 taining to power void pages 3.10-5 & 6 relationship.

37 Specification Specification Change of Operational MCPR See Base Statements in pages 3.10.D 3.10.C limits and add use of K 3.10-7 and 8 of Proposed Tech g

pages 3.10-2 & 3 page 3.10-3 curve.

Spec.

38 Bases statements Bases Statements Delete statements referencing See Extent of Change statement, paragraphs 2 & 3 paragraphs 3 & 4 Type IIIF fuel and add those page 3.10-4 pages 3.10-4 & 5 of CE supplied reload fuel.

39 Bases Statements Add statement referencing See Extent of Change statement.

paragraph 3 power spike penalty for CE page 3.10-6 supplied reload fuel.

40 Bases Statements Bases Statements Change bases of MCPR limits.

See Bases Statements of Proposed paragraph 2 paragraphs 3 & 4 Tech Spec.

page 3.10-6 & 7 page 3.10-7

7 Current Proposed Extent of No.

Tech Spec Tech Spec Change Justification 41 Bases Statements Bases Statements Change of range of operating Results of new analysis, paragraphs 5 & 6 paragraph 1 MCPR statements, page 3.10-7 page 3.10-7 42 References References References 1 and 4 replaced See NED0-24195 page 3.10-8 page 3.10-8 by NEDO-24195.

Section 5.

43 Figure 3.10-1 Figure 3.10-1 Delete MAPLHGR limit for Fuel type IIIF no longer page 3.10-9 page 3.10-9 fuel type IIIF.

in Oyster Creek core.

44 Figure 3.10-2 Figure 3.10-2 Delete MAPLHGR limit for Same as above.

page 3.10-10 page 3.10-10 fuel type IIIF.

45 Figure 3.10-4 Add MAPLHGR limits for fuel Introduction of GE supplied page 3.10-12 types P8DRB-239, P8DRB-265L, reload fuel into Oyster Creek and P8DRB-265H for five core.

loop operation.

46 Figure 3.10-5 Add MAPLilGR limits for fuel Same as above.

page 3.10-13 types P8DRB-239, P8DRB-265L, and P8DRB-26511 for four loop operation.

47 Figure 3.10-6 Add K curve.

Introduction of Kr curve to g

page 3.10-14 define operating limits at other than rated flow conditions.

See Bases Statements paragraphs 3 and 4 Section 4.2 Reactivity Control page 3.10-7 of proposed Tech Spec.

48 Specification Delete 3.9% control rod See Justification for Change 30.

4.2.G density requirement.

page 4.2-2 l

8 Current Proposed Extent of No.

Tech Spec Tech Spec Change Justification 49 Bases Statement Delete statements Same as above.

paragraph 2 reference to control rod page 4.2-3a density requirement.

Section 4.10 ECCS Related Core 1.imits 50 Specification Delete Spec. 4.10.C No Type IIIF in Oyster Creek 4.10.C core.

page 4.10-1 51 Bases Statements Delete statements Same as above, paragraph 2 reference to power void page 4.10-1 and relationship.

4.10-2

_ _ _,