ML20212H413

Application for Amends to Licenses DPR-57 & NPF-5,revising Reporting Requirements of 10CFR50.72 & 50.73,per Generic Ltrs 83-43 & 85-19 Re Primary Coolant Iodine Spiking & Activity Limits.Fee Paid

ML20212H413
Person / Time
Site:	Hatch
Issue date:	02/13/1987
From:	James O'Reilly GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20212H416	List: ML20212H413 ML20212H439
References
GL-83-43, GL-85-19, SL-1878, TAC-55713, TAC-55714, NUDOCS 8703060099
Download: ML20212H413 (17)

Text

Georgia Power Company

. 333 Piedmont Avenue 's Attanta, Georgia 30308 Telephone 404 526 7851 Maing Address:

Post Office Box 4545 Atlanta. Georgia 30302 4

James P. O'Reilly the soutten e+rtec snterr Senior Vice Presidert Nuclear Operations SL-1878

,1070C February 13, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIREMENTS PER 10 CFR PART 50, SECTIONS 50.72 AND 50.73 AND REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES $

Gentlemen:

In accordance with the provisions of 10 CFR 50.90, as required by 10 CFR 50.59(c)(1), Georgia Power Company hereby proposes changes to the Technical Specifications, Appendix A to Operating Licenses DPR-57 and NPF-5 for Plant Hatch Units 1 and 2.

The proposed changes would: (1) incorporate the revised reporting requirements of 10 CFR Part 50, Sections 50.72 and 50.73, as directed by NRC Generic Letter 83-43; and (2) incorporate the revised reporting requirements for primary coolant iodine spiking and remove existing requirements for plant shutdown if primary coolant iodine activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> within a 12-month period, as directed by NRC Generic Letter 85-19.

Enclosure 1 provides detailed descriptions of the proposed changes and the bases for the change request.

Enclosure 2 details the basis for our determination that the proposed f

changes do not involve significant hazards considerations.

Enclosure 3 provides page change instructions for incorporating the proposed changes into the Plant Hatch Units 1 and 2 Technical Specifications.

Acol 0703060099 870213 DR ADOCK0500g1 llS0.00

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- U. S. Nuclear Regulatory Comission February 13, 1987 Page Two s

-The proposed c' hanged Technical Specifications pages follow Enclosure 3.

, Payment of the filing fee in the amount of one hundred and . fifty

. dollars is enclosed. >

c Pursuant to the requirements of 10 CFR 50.91, a copy of this letter

and all applicable enclosures will be sent to Mr. J. L. Ledbetter of the Environmental Protection Division of the Georgia Department of - Natural ,

Resources.

Mr. James -P. O'Reilly states that he~ is Senice Vice President of Georgia Power -Company and is authorized to execute this oath on behalf of i

Georgia Power Company, and ' that to the best of his knowledge and belief, 3

the facts set forth in the letter and enclosures are true.

GEORGIA POWER COPFANY By: mm f. (5y N James P. O'Re1 y Sworn to and subscribed before me this 13th of February 198 .

C- y w Y YtnsAbi Notary Public

, h w'yru m a; r s ,' c.m m

- ' >t i t .'

! Enclosures i

{ c: Georgia Power Company U.S. Nuclear Regulatory Commission

j. Mr. i. T. Beckham Dr. J. N. Grace, Regional Administrator Mr. H. C. . Hix, Jr. Mr. P. Holmes-Ray, Senior Resident

] GO-NORMS Inspector-Hatch i

State of Georgia Mr. J. L. Ledbetter 1

i 1070C i

m _ ._ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _

ENCLOSURE 1 NRC' DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS-1 AND 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIREMENTS PER 10 CFR PART 50, SECTIONS 50.72 AND 50.73 AND REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES BASIS FOR CHANGE REQUEST Proposed Change 1:

This proposed change would add to the Unit 1 Technical Specifications Definitions Section the ' term REPORTABLE EVENT. This proposed change would also delete from the Unit 2 Technical Specifications Definitions section the term REPORTABLE OCCURRENCE and - replace it with the term REPORTABLE

- EVENT, as follows:

A " REPORTABLE EVENT" shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

This change would appear in Unit 1 Technical Specifications Section 1.0, item III. The change would also appear in Unit 2 Technical Specifications Section 1.0.

Basis for Proposed Change:

This change would make modifications of an administrative nature to the Technical Specifications, as directed by NRC Generic Letter 83-43, in order to reflect the current reporting requirements of 10 CFR Part 50,. Sec-tion 50.73. Therefore, the definition REPORTABLE EVENT has been added in  :

the Unit 1 Technical Specifications and the term REPORTABLE OCCURRENCE has been replaced in the Unit 2 Technical Specifications with the term REPORTABLE EVENT. This change is consistent with the model technical specification presented in the Standard Technical Specifications format in -

NRC Generic Letter 83-43. This change to the Technical Specifications, which is proposed at the request of the NRC, is clarifying in nature and does not represent any change to the design, operation, or safety of the plant.

Proposed Change 2:

This proposed change would relocate the reporting requirements for the failure or malfunction of any safety / relief valve from Section 6.9.1.12 of the ' Units 1 and 2 Technical Specifications to Section 3.6.H.l.a of the Unit 1 Technical Specifications and Section 3.4.2.1.f of Unit 2 Technical Specifications. The written followup report requirement would be changed from 14 days to 30 days.

6 1070C El-1 2/13/87 i

ENCLOSURE 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIREMENTS PER 10 CFR PART 50, SECTIONS 50.72 AND 50.73 AND REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES BASIS FOR CHANGE REQUEST Basis for Proposed Change:

This reporting requirement is being relocated rather than deleted, because certain types of safety / relief valve malfunctions (e.g., the opening of a relief valve at a pressure lower than the setpoint) do not fall under the provisions of 10 CFR 50.72(b)(1)(ii) or 10 CFR 50.73(a)(2)(fi). These types of mal functions should still be reported in accordance with Item II.K.3.3 of NUREG 0737. Failures or malfunctions of safety / relief valves, which do fall under the provisions of 10 CFR 50.72 and 10 CFR 50.73, would still be subject to the reporting requirements contained therein. The change in the written followup report requirement from 14 to 30 days is made to be consistent with the requirements of 10 CFR 50.73.

Proposed Change 3:

This proposed change would delete from the Unit 2 Technical Specifications the Special Report requirements for: (1) High Pressure Coolant Injection (HPCI) system actuation contained in Section 3.5.1.c, (2) Core Spray System (CSS) actuation contained in Section 3. 5. 3.1. a . 3, and (3) Low Pressure Coolant Injection (LPCI) system actuation contained in Section 3.5.3.2.a.4.

Basis for Proposed Change:

These Special Report requirements would be deleted, because any actuation of these Emergency Core Cooling Systems (ECCS) is required to be reported under the:

1. Immediate notification provisions of 10 CFR 50.72(b)(1)(iv) for "Any event that results or should have resulted in Emergency Core Cooling System (ECCS) discharge into the reactor coolant system as a result of a valid signal."

2. Immediate notification provisions of 10 CFR 50.72(b)(2)(ii) for "Any event or condition that resul ts in manual or automatic actuation of an Engineered Safety Feature (ESF)." Each system identified above as part of the ECCS is also an ESF system.

Also, written notification within 30 days is required by 10 CFR 50.73 (a)(2)(iv), which states that the licensee shall report "Any event or 1070C El-2 2/13/87

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. ENCLOSURE 1

REQUEST TO REVISE TECHNICAL SPECIFICATIONS

REVISE REPORTING REQUIREMENTS PER 10 CFR PART 50, '

SECTIONS 50.72 AND 50.73 AND i- REPORTING REQUIREMENTS ON PRIMARY COOLANT 10DINF. SPIKES BASIS FOR CHANGE REQUEST i

condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF)." Since 10 CFR 50.73(g) states:- "The requirements contained in this section replace all existing requirements for Itcensees  ;

to report ' Reportable Occurrences' as defined in individual plant Technical' Specifications," these sections are no longer needed and, therefore, should L be deleted.

4

Proposed Change 4

This proposed change would relocate the reporting requirements for Type B and Type C Leakage Tests from- Unit 1 and Unit 2 Technical Specifications Sections 6.9.1.13 (which are proposed for deletion) to Sections 4.7. A.2.f

and 4.7.A.2.g of the Unit 1 Technical Specifications and to Section

4. 6.1. 2. d of the Unit 2 Technical Specifications. The reporting requirements will continue to reflect the fact that one 30-day written

, report may be submitted within 30 days of the first leakage test failure which occurs during the outage, and that all other leakage test failures discovered during the outage will be reported in a revision to the original report, due within 30 days following the completion of the outage. ,

Basis for Proposed Change:

Although the reporting requirements are covered under the provisions of 10 CFR 50.73(a)(2)(fi), this section is being retained in the Technical Specifications in order to more clearly define the following: ,

) 1. The start of the 30-day period within which a 30-day report is due l during an outage in case of a leakage test failure.

2. The manner in which subsequent leakage test failures occurring j during an outage are to be reported (provided by Amendment 100 to .

the Unit 1 Technical Specifications and Amendment 37 to the Unit 2 Technical Specifications).

l This relocation of reporting requirements is consistent with the requirements of 10 CFR 50.73, is clarifying in nature, and does not represent any change to the design, operation, or safety of the plant.  !

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1 j 1070C El-3 2/1187 i

L EHCLOSURE 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIREMENTS PER 10 CFR PART 50, SECTIONS 50.72 AND 50.73 AND REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES BASIS FOR CHANGE REQUEST Proposed Change 5:

This proposed change would revise the wording in some Unit 2 Technical Specifications sections currently requiring Special Reports or other routine reporting of events in lieu of a Licensee Event Report. This revised wording would state that these reports would be submitted in lieu of any other report required by 10 CFR 50.73 and pursuant to Specification 6.9.2, except for Unit 2 reports concerning diesel generator failures which would be submitted pursuant to 10 CFR 50.73 or Specification 6.9.2, as applicable. The affected sections are: Specifications, 3.3.6.2.a, 4.3.6.2.2, and 4.8.1.1.4.

Basis for Proposed Change:

Huclear Regulatory Conission Generic Letter 83-43 states:

Some technical specifications currently require Special Reports or othc. routine reporting of events in lieu of a Licensee Event Report. Such reports are still required but the technical spec /fication wording will need revision. These changes, where applicable, should also be included in your amendment request to modify your technical specifications.

Therefo e, the references stated in the reporting requirements have been changed to show the current regulations requiring the reports. This change to the Technical Specifications, which is proposed at the request of the NRC, ?s clarifying in nature and does not represent any change to the design, operation, or safety of the plant.

Proposed Change 6:

The proposed change would delete from Unit 1 Technical Specifications Sections 3.11.D and Bases 3.11.D. This section presently provides that a Reportable Occurrence report shall be submitted for any event in which any of the limiting values of the Average Planar Linear Heat Generation Rate (APLHCR), the Linear Heat Generation Rate (LHGR), or the Minimum Critical Power Ratio (PCPR) are exceeded.

1070C El-4 2/13/87

h ENCLOSURE 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIREMEN13 PER 10 CFR PART 50, SECTIONS 50.72 AND 50.73 AND REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES BASIS FOR CHANGE REQUEST Basis for Proposed Change:

10 CFR 50.73(g) states: "The requirements contained in this section replace all existing requirements for licensees to report ' Reportable Occurrences' as defined in individual plant Technical Specifications," it is therefore no longer necessary to retain a specific section in the Unit 1 Technical Specifications delineating the reporting requirements for this type of event. If a limiting value of APLHGR, LHGR, or FEPR is exceeded, and the required Technical Specification Action statement is not met, reporting under 10 CFR 50.73 (a)(2)(1)(B) is appropriate. This change to the Unit 1 Technical Specifications, which is proposed at the request of the NRC, is administrative in nature and does not represent any change to the design, operation, or safety of the plant.

Proposed Change 7:

This proposed change would revise the Unusual or Important Events reporting requirements listed in Section 4.2 of the Unit I and 2 Environmental Technical Specifications (ETS) so that reports are made as required by 10 CFR 50.72 and 10 CFR 50.73 rather than in accordance vf th ETS Sec-tion 5.6.2 which would be deleted. Also, the proposed changa would reword the reporting requirements stated in Section 4.3 of the Unit 1 and 2 ETS so that in the case of a reportable event in which a limit specified in a relevant permit or certificate issued by another Federal, State, or local agency is exceeded, the report would be submitted within the time limit specified by tl.e reporting requirements of the corresponding certification or permit issued pursuant to Section 401 or 402 of PL 92-500. The report which would be sent to the NRC would consist of a copy of the report which would be made to the Georgia Department of Natural Resources, Environmental Protection Division. These reportable event reporting requirements are currently contained in Section 5.6.2. In addition, the proposed change 1070C El-5 2/13/87

ENCLOSURE 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REOUIREMENTS PER 10 CFR PART 50, SECTIONS 50.72 AND 50.73 AND REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES BASIS FOR CHANGE REQUEST would delete Sections 5.6.2 of the Unit 1 and 2 ETS which contains the reporting requirements for non-routine reports.

Basis for Proposed Change:

Reporting requirements for unusual or important environmental events are covered under the provisions of 10 CFR 50.72(b)(2)(vi), 10 CFR 50.73 (a)(2)(tii) and 10 CFR 50.73(a)(2)(x). Therefore, the reference to the reporting requirements presented in 10 CFR 50.72 and 10 CFR 50.73 is appropriate. The rewording of the reporting requirements stated in Section 4.3 does not constitute a change in the reporting requirements, but is merely a relocation of those requirements from Section 5.6.2 to Section 4.3, and a replacement of the term REPORTABLE OCCURRENCE with the term REPORTABLE EVENT. Consequently, since the reporting requirements for non-routine-type reports are adequately presented in Sections 4.2 and 4.3, Section 5.6.2 is no longer needed and is, therefore, deleted. This change to the ETS is clarifying in nature and does not represent any change to the design, operation, or safety of the plant.

Proposed Change 8:

The proposed change would: (1) remove from Section 3.4.4.a.1 of the Unit 2 Technical Specifications the reference to Technical Specifications Section 6.9.1.9 for reporting requirements for reactor coolant system conductivity or chloride concentration exceeding specified limits, and (2) add to Section 3.4.4.a.1 of the Unit 2 Technical Specifications the Special Report requirements pursuant to Technical Specifications Section 6.9.2 in lieu of any other report required by 10 CFR 50.73.

Basis for Proposed Change:

Huclear Regulatory Comission Generic Letter 03-43 states:

Some technical specifications currently require Special Reports or other routine reporting of events in lieu of a Licensco Event Report. Such reports are still required but the technical specification wording will need revision. These changes, where applicable, should also be included in your amendment request to modify your technical specifications.

1070C El-6 2/13/87

ENCLOSURE 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIREMENTS PER 10 CFR PART 50, SECTIONS 50.72 AND 50.73 AND REPORTING REQtIMElENTS ON PRIMARY COOLANT IODINE SPIKES BASIS FOR CHANGE REQUEST This change would accomplish this intent with the removal of these items from the Radioactive Effluent Release Report and the placing of them under appropriate provisions for Special Reports. The requirement for a Special Report is appropriate, because reporting of a violation of the conductivity or chloride concentration limit (during a time period less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) is not required until unit operation under these conditions exceeds 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year. Operation at these conditions for more than 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year is allowed, but a Special Report must be submitted to the NRC. This change to the Unit 2 Technical Specifications, which is proposed at the request of the NRC, is clarifying in nature and does not represent any change to the design, operation, or safety of the plant.

prpposed

_r Change 9:

TFis proposed change would delete from Section 4.6.1.5 of the Unit 2 Technical Specifications the sentence: "Any abnormal degradation of the primary containment detected during the required inspections shall be reported to the Commission pursuant to Specification 6.9.1." The " required inspections" occur during shutdown.

Basis for proposed Change:

This reporting requirement would be deleted, because any event such as this, found while the reactor is shut down, that, had it been found while the reactor was in operation, would have resulted in the nuclear power plant, (including its principal safety barriers) being seriously degraded, requires a Four-Hour Report under the provisions of 10 CFR 50.72(b)(2)(1).

In addition, any event or condition such as this which resulted in the condition of the nuclear power plant, including its principal sa fety barriers being seriously degraded would require a Licensee Event Report written notification within 30 days under the provisions of 10 CFR 50.73 (a)(2)(ii). Since 10 CFR 50.73(g) states: "The requirements contained in this section replace all existing requirements for licensees to report

'p.eportable Occurrences' as defined in individual plant Technical Specificattuns", the subject sentence is no longer needed and, therefore, should be deleted.

0169F El-7 2/13/87

ENCLOSURE 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIREMENTS PER 10 CFR PART 50, SECTIONS 50.72 AND 50.73 AND REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES BASIS FOR CHANGE REQUEST Proposed Change 10:

This )roposed change would revise the ADMINISTRATIVE CONTROLS sectionr and assoc <ated TABLE OF CONTENTS and INDEX to reflect the revised immediato notification requirements of 10 CFR 50.72 and the Licensco Event Report system requirements of 10 CFR 50.73. Unit 1 Technical Specifications Sections 6.5.1.6. f, 6.5.2.7.g, 6.6, 6. 6.1. a . 6. 6.1. b , 6.7.1.b, 6.7.1.c, 6.7.1.d, 6.9, 6.10.1. c . and Table 6. 9.1. 7 -1 would be appropriately reworded; and Sections 6.9.1.11, 6.9.1.12 and 6.9.1.13 would be deleted.

Unit 2 Technical Specifications Section 6.9 of the Index, Sections 6.5.1.6.f, 6.5.2.7.g. 6.6, 6.6.1.a. 6.6.1.b, 6.7.1.b. 6.7.1.c, 6.7.1.d, 6.9, 6.10.1.c, and Table 6.9.1.7-1 would be appropriately reworded; and Sections 6.9.1.11, 6.9.1.12, and 6.9.1.13 would be deleted.

Basis for Proposed Chango:

This chango would make modifications of an administrative nature to the Unit 1 and 2 Technical Specifications, as specifically directed by Generic Letter 84-43, in order to incorporate the current reporting requirements stated in of 10 CFR Part 50, Sections 50.72 and 50.73. Since paragraph (g) of Section 50.73 specifically states: "The requirements contained in this section replace all existing requirements for licensees to report

' Reportable Occurrences' as defined in individual plant Technical Specifications", the reporting requirements incorporated into the Administrative Controls sections of the Technical Specifications have bcon appropriately modified. These changes are consistent with the model technical specification presented in Standard Technical Specifications format in NRC Genoric Lotter 83-43. This change to the Technical Specifications, which is proposed at the request of the NRC, is clarifying in nature and does not represent any change to the design, operation, or safety of the plant.

Proposed Chango 11:

This pronosed change would make the following revisions to the Technical Specifications pursuant to Generic Lotter 85-19. " Reporting Requirements on Primary Coolant Iodino Spikes," dated September 27, 1905.

In the Unit 1 Technical Specifications:

1. Delete tho second paragraph of Section 3.6.F.1 which specifies iodine activity limits within a 12-month period.

1070C El-0 2/13/07

L k ENCLOSURE 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIREMENTS PER 10 CFR PART 50, SECTIONS 50.77 AND 50.73 AND REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES DASIS FOR CHANG EREQUEST

2. Change the third paragraph of Section 3.6.F.1 to redefine the activity concentration limits.

3. Change the last paragraph of Section 4.6.F.1 to remove the 30-day reporting requirement.

4. Add Saragraph 6.9.1.5.c (relocato existing paragraph 6.9.1.5.c to 6.9. 5.d) to include requirements for an Annual Report.

In the Unit 2 Technical Specifications:

1. Delete paragraph 3.4.5.a.1 which limits iodino activity limits in a 12-month period.

2. Renumber paragraph 3.4.5.a.2 to 3.4.5.a.1 and redoffne the activity concentration limits.

3. Renumber paragraph 3.4.5.a.3 to 3.4.5.a.2.

4 Chango paragraph 3.4.5.b.1 to remove the REPORTABLE OCCURRENCE report requirement.

5. Change paragraph 3.4.5.b.2 to remove the 92-day Special Report requirement.

6.

Add 1arag)raph 6.9 '.5.d to include 6.9.1.5.c requirements (relocatoforexisting paragraph an Annual Report. 6.9.1.5.c to Basis for Propor.cd Chango:

This change would make modifications to the Technical Specifications, as directed by Concric Lottor 85-19. The reporting requirements for iodino spiking contained in the Technical Specifications would be changed from a short-term report to an item for inclusion in the Annual Report. The information to bo included in the Annual Report is similar to that previously required but has boon changed to more clearly designato the results to bo included from the specific activity analysis and to doloto the information regarding fuel burnup by core region. Also, the existing requirements contained in the Technical Specifications for plant shutdown, if coolant fodine activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12-month portod, would be removed.

1070C El -9 2/13/87

ENCLOSURE 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTIhG REQUIREMENTS PER 10 CFR PART 50, SECTIONS 50.72 AND 50.73 AND REPORTING REQllIREMENTS ON PRIMARY C00lTRT IODINE SPIKES BASIS FOR CHANGE ~ REQUEST These changes are justified, because as provided in Generic Letter 85-19, the quality of nuc1 car fuel has been greatly improved over the past decade with the result that normal coolant iodine activity (i.e., in the absence of iodino spiking) is well below the limit. Appropriato actions would be initiated long before accumulating 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> above the iodine activity limit. In addition, 10 CFR 50.72 (b)(1)(ii) requires the HRC to be imediately notified of fuel cladding failures that exceed expected values or that are caused by unexpected factors. Therefore, this Technical Specification limit is no longer necessary on the basis that proper fuel management and existing reporting requirements should precludo ever approaching the limit. Plant llatch would continue to monitor iodine activity in the primary coolant and take responsible actions to maintain it at a reasonably low level (i.e., accumulated time with high f odino activity would not approach 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />).

1070C El-10 2/13/87

uk ENCLOSURE 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN 1. HATCH NUCLEAR PLANT UNITS 1 AND 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIRDfEHT5 PER 10 CFR PART 50, SECTIONS 5072 AND 50737RD REPORTING REQGIRERETITS ON PRIRARY CDDURT IODINE SPIKES '

10 CFR 50.92 EVALUATIDh Pursuant to 10 CFR 50.92, Coorgia Power Company has evaluated the enclosed proposed amendments for the Plant Hatch Units 1 and 2 Technical Specifications and has determined that their adoption would not involve a significant hazards consideration. The basis for this determination is as follows:

Proposed Changes 1 through 10:

Incorporato revised imediato notification re airements according to revised Section 50.72 of Title 10 of the Codo of Federal Regulations, offectivo January 1, 1984. Incorporato revised Licensco Event Report System requirements according to new Section 50.73 of Title 10 of the Code of Federal Regulations, offectivo January 1,1984 Basis for Proposed Changes:

These changos are consistent with Item (1) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,070 of the Register, dated April 6, 1983. Those changos would make modifications of an administrativo nature to the Technical Specifications, as directed by NRC Generic letter No.

03-43, in order to incorporato current reporting requirements of 10 CFR Part 50, Sections 50.72 and 50.73.

These changos do not involve a significant increase in the probability or consequences of an accident previously evaluated, because no accident analysis is affected by this change. Those changes reflect reporting requirements only and have not offcct on plant operations or accident analysos.

Those changes do not create the possibility of a new or different kind of accident from any previously evaluated, becauso no accident analysis is af fected nor is the need for a new accident analysis created by these changes. Those administrative changes only reviso reporting requirements and have no of fect on plant operations. Thus, the changos do not create the possibility of a now or different kind of accident.

1070C E21 2/13/07

ENCLOSURE 2 REQUEST TO REVISE TECllHICAL SPECIFICATIONS:

REVISTRUDRTIhG REQUIRINGTS PER 10 CFR PART 50, SECTIONS 50.7FAND 50.73 AND REPORTING REQtIIRTRGT5~0TP1TIRARTC50CKHT10DIllE SPIKES -

10 CFR 50.9'2 EVALUATT0h Those changes do not involve a significant reduction in a margin of safety, because those administrativo changes only reviso reporting requirements.

No chango is made to the design or operation of the plant and, therefore, the margin of safety is preserved.

Proposed Chango 11:

Reduce the reporting requirements for primary coolant iodino spiking from a short-term report to an item for inclusion in the Annual Report. Removo existing requirements to shut down the plant if primary coolant fodino activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> within a 12-month period.

Basis for Prop,osed Chango:

This change would make modifications to the Technical Specifications, as directed by NRC Generic Lotter 85-19, to reviso the reporting requirements for iodino spiking from a short-term report to an item for inclusion in the Annual Report. The climination of plant shutdown requirements, if the primary coolant iodino activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12-month period, deletes an unnecessary Technical Specifications requirement, as directed by Generic Lotter 05-19, since other factors should preclude ever approaching the limit.

This chango does not involve a significant increase in the probability or consequences of an accident previously evaluated, because no accident analysis is affected by thoso change. The revision to the reporting requiremont is an administrative chango. The climination of the shutdown requiremont doos not allow the primary coolant fodine activity limits to be approached, sinco appropriato actions would be initiated long before accumulating 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> above the iodino activity limit. Also, the NPC is required to be notiflod of fuel cladding failures which exceed expected values or that are caused by unospected factors. Thorofore, this chango cannot increase the probability or consequences of an accident.

This chango does not create the possibility of a new or different kind of accident from any previously evaluated, because no accident analysis is affected nor 15 the need for a new accident analysis created by this change. This chango is proposed pursuant to Concric Lotter 0519.

10700 E2-2 2/13/07

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< 1 ENCLOSURE 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVI5CRUURTIhG REQUIRU1ENTS PER 10 CFR P3 tit 50, 5ECT!0H5'5072'ARD 507TAND REPORTING REQtJIREflERT57N PRIMARY ~C50EART IODINE SPIKES 1D7FR 50.92 EVAUTATIDN This change does not involvo a significant reduction in a margin of safety. The reporting requirement chango is entirely administrative in naturo. The chango does not affect the Technical Specifications margin of safety, becauso it does not chango or eliminato any Limiting Conditions for Operation (except those related to reporting), equipment operability requirements (including definition of operabili ty), trip settings or sotpoints, allowable trip sottings or sotpoints Limiting Safety :;ystem Settings, or Safety Limits. The elimination of the shutdown requirement, if primary coolant iodino activity limits are exceeded for 800 houi's in a 12-month period, does not reduce the margin of safoty in the Technical Specifications because appropriato actions would be initiated long before accumulating 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> above the iodino activity limit and the NRC is required to be notified of fuel cladding failures that exceed expected values or that are caused by unexpected factors.

1070C [2-3 2/13/87

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i ENCLOSURE 3 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 i EDWIN 1. HATCH NUCLEAR PLANT UNITS I AND 2 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIREMENT 5 PER 10 CFR PART 50, 5ECTION5 50.72 AllD 50.73 AND REPORTING REQlTIRERDIT!n)TPRTHARTt0DEKRT100INE SPIKES The proposed changes to Technical Specifications and Environmental Technical Specifications (Appendices A and B to Operating License DPR-57) would be incorporated as follows:

UNIT 1 Remove Page Insert Page vi vi 1.0-10 1.0-10 3.6-4 3.6-4 3.6-5 3.6-5 3.6-9 3.6-9 3.7-6 3.7-6 3.7-6a 3.7-6a 3.11-2a 3.11-2a i 3.11-5 3.11-5 l 6-7 6-7  ;

6-10 6-10 l 6-12 6-12 6 13 6-13 6-14 6-14 6-15 6-15 6-15b 6-15b 6-15d 6-15d 6-16 6-16 6-17 6-17 6-18 6-18 4-1(ETS) 4-1(ETS) 4-2(ETS) 4-2(ETS) ,

5-8(ETS) 5-8(ETS) 1070C E3-1 2/13/87 l

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ENCLOSURE 3 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

REVISE REPORTING REQUIREMENTS PER 10 CFR PART 50, SECTIONS 50.72 AND 50.73 AND REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES The proposed changes to Technical Specifications and Environmental Techn< cal Specifications (Appendices A and B to Operatin9 License NPF-5) would be incorporated as follows:

UNIT 2 Remove Pago Insert Page iia iia XVI XVI 1-9 1-9 3/4 3-47 3/4 3-47 3/4 4-4 3/4 4-4 3/4 4-7 3/4 4-7 3/4 4-10 3/4 4-10 3/4 4-11 3/4 4-11 3/45-1 3/45-1 3/4 5-4 3/4 5-4 3/4 5-7 3/4 5-7 3/4 6-5 3/4 6-5 3/4 6-8 3/4 6-8 3/4 8-7 3/4 8-7 6-6 6-6 6-9 6-9 6-11 6-11 6-12 6-12 6-13 6-13 6-14 6-14 6-14a 6-14a 6-14b 6-14b 6-14d 6-14d 6-15 6-15 6-16 6-16 6-17 6-17 4-1(ETS) 4-1(ETS) 4-2(ETS) 4-2(ETS) 5-8(ETS) 5-8(ETS) 1070C E3-2 2/13/87