Text

License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application.
	ML16214A252
Person / Time
Site:	Hatch, Vogtle, Farley
Issue date:	07/28/2016
From:	Wheat J; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-16-0091
	Download: ML16214A252 (149)
	v • d • e

r Justin T. Wheat Southern Nuclear Nuclear Licensing Manager Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham , AL 35242 Tel 205 .992 .5998 Fax 205.992 .7601 SOUTHERN NUCLEAR II..\

A SOUTHERN COMPANY July 28, 2016 Docket Nos.: 50-348 50-321 50-424 NL-16-0091 50-364 50-366 50-425 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, "TS lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing," and to Request an Alternative to the ASME Code Ladies and Gentlemen:

In accordance with the provisions of 10 CFR 50.90 Southern Nuclear Operating Company (SNC) is submitting a request for an amendment to the Technical Specifications (TS) for Joseph M. Farley Nuclear Plant (FNP) , Units 1 and 2, Edwin I. Hatch Nuclear Plant (HNP), Units 1 and 2, and Vogtle Electric Generating Plant (VEGP) , Units 1 and 2.

The proposed change revises the Technical Specifications (TS) at FNP , HNP and VEGP to eliminate the "lnservice Testing Program" from the TS 5.5 "Programs and Manuals" section and to add a new defined term , "INSERVICE TESTING PROGRAM," to the TS 1.1 "Definitions" section. This request is consistent with TSTF-545, Revision 3, "TS lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ," and is submitted in compliance with the timeframe requirement for continuing to receive enforcement discretion which was established by the February 24 , 2012 Enforcement Guidance Memorandum (EGM) 12-001, "Dispositioning Noncompliance with Administrative Controls Technical Specifications Programmatic Requirements that Extend Test Frequencies and Allow Performance of Missed Tests."

Pursuant to 10 CFR 50.55a(z), the application also proposes an alternative to the testing frequencies in the American Society of Mechanical Engineers (ASME)

Operation and Maintenance (OM) Code , by adoption of approved Code Case OMN-20 , "lnservice Test Frequency," for the current 1O year lnservice Testing (IST) interval for FNP and VEGP. HNP previously received approval to utilize OMN-20 for the current 10-year interval, which started 1/1/2016.

U. S. Nuclear Regulatory Commission NL-16-0091 Page 2 provides a description of the proposed changes, confirmation of applicability of the published safety evaluation , and plant-specif ic variations. provides the affected TS pages marked up to show the proposed changes, while Enclosure 3 provides revised (clean typed) TS pages and Enclosure 4 provides, for information only, the affected TS Bases pages marked up to show the associated Bases changes. provides the request for an alternative to the ASME Code.

SNC requests approval of the proposed license amendments by February 28, 2017.

The proposed changes would be implemented within 120 days of issuance of the amendment.

In accordance with 10 CFR 50.91 (b)(1 ), "State Consultation," a copy of this application and its reasoned analysis about no significant hazards considerations is being provided to the designated Alabama and Georgia officials.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

Mr. J. T. Wheat states he is Nuclear Licensing Manager of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and , to the best of his knowledge and belief, the facts set forth in this letter are true.

Respectfully submitted, J. T. Wheat Nuclear Licensing Manager JTW/DWD/lac Sworn to and subscribed before me this 1

Z.. '1/1" day of ::JU 4 , 2016.

t'.:kk.:M+

Notary Public My commission expires: t/ z(z_.o/ 8

Enclosures:

1. Basis for Proposed Change

2. FNP, HNP, and VEGP Technical Specification Marked Up Pages

3. FNP, HNP, and VEGP Technical Specification Clean Typed Pages

4. FNP, HNP, and VEGP Technical Specification Bases Marked Up Pages (for information only)

5. Description and Assessment of the Proposed Alternative to the ASME Code

U. S. Nuclear Regulatory Commission NL-16-0091 Page 3 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. M. D. Meier, Vice President - Regulatory Affairs Ms. C. A. Gayheart, Vice President - Farley Mr. D. R. Vineyard, Vice President - Hatch Mr. B. K. Taber, Vice President - Vogtle 1 & 2 Mr. D. R. Madison, Vice President - Fleet Operations Mr. B. J. Adams, Vice President - Engineering Mr. C. R. Pierce, Regulatory Affairs Director Ms. B. L. Taylor, Regulatory Affairs Manager - Farley Mr. G. L. Johnson, Regulatory Affairs Manager - Hatch Mr. G. W. Gunn, Regulatory Affairs Manager - Vogtle 1 & 2 RType : CFA04.054; CHA02.004; CVC7000 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. S. A. Williams, NRR Project Manager - Farley Mr. M. D. Orenak, NRR Senior Project Manager - Hatch Mr. R. E. Martin, NRR Senior Project Manager - Vogtle 1&2 Mr. P. K. Niebaum, Senior Resident Inspector - Farley Mr. D. H. Hardage, Senior Resident Inspector - Hatch Mr. L. M. Cain, Senior Resident Inspector - Vogtle 1 & 2 Alabama Department of Public Health Dr. T. M. Miller, State Health Officer State of Georgia Mr. J. H. Turner, Director - Environmental Protection Division

Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, "TS lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing," and to Request an Alternative to the ASME Code Enclosure 1 Basis for Proposed Change to NL-16-0-091 Basis for Proposed Change Table of Contents 1.0 Description 2.0 Assessment 3.0 Regulatory Analysis 4.0 Environmental Evaluation E1-1 to NL-16-0091 Basis for Proposed Change

1.0 DESCRIPTION

The proposed change eliminates the Technical Specifications (TS) , Section 5.5, "lnseNice Test (IST) Program ," to remove requirements duplicated in American Society of Mechanical Engineers (ASME) Code for Operations and Maintenance of Nuclear Power Plants (OM Code) , Case OMN-20 , "lnservice Test Frequency." A new defined term , "lnservice Testing Program ," is added to TS Section 1.1, "Definitions. The proposed change to the TS is consistent with TSTF-545 , Revision 3, "TS lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ."

2.0 ASSESSMENT 2.1 Appl icability of Published Safety Evaluation Southern Nuclear Operating Company (SNC) has reviewed the model safety evaluation provided to the Technical Specifications Task Force in a letter dated December 11 , 2015 (NRC ADAMS Accession No. ML15314A305). This review included a review of the NRC staff's evaluation , as well as the information provided in TSTF-545. As described in the subsequent paragraphs , SNC has concluded that the justifications presented in TSTF-545 ,

and the model safety evaluation prepared by the Nuclear Regulatory Commission (NRC) staff are applicable to Joseph M. Farley Nuclear Plant (FNP) , Units 1 and 2, Edwin I. Hatch Nuclear Plant (HNP) , Units 1 and 2, and Vogtle Electric Generating Plant (VEGP) , Units 1 and 2, and justify this amendment for the incorporation of the changes to FNP Units 1 and 2, HNP Units 1 and 2, and VEGP Units 1 and 2 TS.

FNP Unit 1 was issued a construction permit on August 16, 1972 and the provisions of 10 CFR 50.55a(f)(2) are applicable.

FNP Unit 2 was issued a construction permit on August 16, 1972 and the provisions of 10 CFR 50.55a(f)(2) are applicable.

HNP Unit 1 was issued a construction permit on September 30 , 1969 and the provisions of 10 CFR 50 .55a(f)(1) are applicable.

HNP Unit 2 was issued a construction permit on December 27, 1972 and the provisions of 10 CFR 50.55a(f)(2) are applicable.

VEGP Unit 1 was issued a construction permit on June 28, 1974 and the provisions of 10 CFR 50.55a(f)(2) are applicable.

VEGP Unit 2 was issued a construction permit on June 28, 1974 and the provisions of 10 CFR 50.55a(f)(2) are applicable.

2.2 Variations SNC is proposing the following variations from the TS changes described in the TSTF-545, or in the applicable parts of the NRC staff's model safety evaluation dated December 11 ,

E1-2 to NL- 16-0091 Basis for Proposed Change 2015 . These variations do not affect the applicability of TSTF-545 or the NRC staff's model safety evaluation to the proposed license amendments.

FNP Units 1 and 2 , HNP Units 1 and 2, and VEGP Units 1 and 2 TS utilize different numbering than the Standard Technical Specifications on which TSTF-545 was based .

Specifically, FNP Units 1 and 2 and VEGP Units 1 and 2 differ from TSTF-545 in that while the numbering for the section to be deleted (i.e. 5.5.8) is consistent with the applicable Standard Technical Specifications, the proposed revision labels section 5.5.8 as "Not Used" and so maintains the existing numbering for subsequent sections in the TS and corresponding Bases .

HNP Units 1 and 2 TS differ in numbering from TSTF-545 in that the numbering for the section to be deleted (i.e. 5.5.6) differs from the applicable Standard Technical Specifications numbering (5 .5.7) ; in this case, since the proposed revision labels section 5.5.6 as "Not Used" and maintains the existing numbering for the subsequent sections , the proposed revision will result in the numbering of the subsequent sections of the TS and corresponding Bases becoming consistent with TSTF-545.

Also , variant terminology such as "lnservice Testing Plan ," "lnservice Test Program" or "IST Program" is sometimes used in place of "lnservice Testing Program" in the existing FNP and VEGP Units 1 and 2 TS and Bases, including usage in surveillance requirement (SR) statements. These terms are replaced with "INSERVICE TESTING PROGRAM" in the proposed license amendments.

These differences are administrative in nature and do not affect the applicability of TSTF-545 to FNP Units 1 and 2 , HNP Units 1 and 2, and VEGP Units 1 and 2 TS.

3.0 REGULATORY ANALYSIS

3 .1 No Significant Hazards Consideration Determination SNC requests adoption of the Technical Specification (TS) changes described in TSTF-545 , "TS lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ," which is an approved change to the Improved Standard Technical Specifications (ISTS) , into the FNP Units 1 and 2, HNP Units 1 and 2 , and VEGP Units 1 and 2 TS. The proposed change revises the TS Chapter 5, "Administrative Controls," Section 5.5, "Programs and Manuals ," to delete the "lnservice Testing (IST) Program" specification .

Requirements in the IST Program are removed , as they are duplicative of requirements in the American Society of Mechanical Engineers (ASME) Operations and Maintenance (OM) Code, as clarified by Code Case OMN-20, "lnservice Test Frequency." Other requirements in Section 5.5 are eliminated because the Nuclear Regulatory Commission (NRC) has determined their appearance in the TS is contrary to regulations . A new defined term ,

"INSERVICE TESTING PROGRAM ," is added , which references the requirements of Title 10 of the Code of Federal Regulations (10 CFR) , Part 50 , paragraph 50.55a(f).

SNC has evaluated whether or not a significant hazards consideration is involved with the proposed amendments by focusing on the three standards set forth in 10 CFR 50.92 , "Issuance of amendment," as discussed below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

E1-3 to NL-16-0091 Basis for Proposed Change Response: No.

The proposed change revises TS Chapter 5, "Administrative Controls ," Section 5.5 ,

"Programs and Manuals," by eliminating the "lnservice Testing Program" specification .

Most requirements in the lnservice Testing Program are removed , as they are duplicative of requirements in the ASME OM Code , as clarified by Code Case OMN-20 , "lnservice Test Frequency." The remaining requirements in the Section 5.5 IST Program are eliminated because the NRC has determined their inclusion in the TS is contrary to regulations . A new defined term, "INSERVICE TESTING PROGRAM ," is added to the TS , which references the requirements of 10 CFR 50 .55a(f) .

Performance of inservice testing is not an initiator to any accident previously evaluated.

As a result, the probability of occurrence of an accident is not significantly affected by the proposed change. lnservice test frequencies under Code Case OMN-20 are equivalent to the current testing period allowed by the TS with the exception that testing frequencies greater than 2 years may be extended by up to 6 months to facilitate test scheduling and consideration of plant operating conditions that may not be suitable for performance of the required testing . The testing frequency extension will not affect the ability of the components to mitigate any accident previously evaluated as the components are required to be operable during the testing period extension.

Performance of inservice tests utilizing the allowances in OMN-20 will not significantly affect the reliability of the tested components. As a result, the availability of the affected components, as well as their ability to mitigate the consequences of accidents previously evaluated , is not affected .

Therefore , the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed change does not alter the design or configuration of the plant. The proposed change does not involve a physical alteration of the plant; no new or different kind of equipment will be installed . The proposed change does not alter the types of inservice testing performed . In most cases , the frequency of inservice testing is unchanged . However, the frequency of testing would not result in a new or different kind of accident from any previously evaluated since the testing methods are not altered.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated .

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The proposed change eliminates some requirements from the TS in lieu of requirements in the ASME Code , as modified by use of Code Case OMN-20.

Compliance with the ASME Code is required by 10 CFR 50.55a. The proposed change E1-4 to NL-16-0091 Basis for Proposed Change also allows inservice tests with frequencies greater than 2 years to be extended by 6 months to facilitate test scheduling and consideration of plant operating conditions that may not be suitable for performance of the required testing . The testing frequency extension will not affect the ability of the components to respond to an accident as the components are required to be operable during the testing period extension .

The proposed change will eliminate the existing TS SR 3.0.3 allowance to defer performance of missed inservice tests up to the duration of the specified testing frequency , and instead will require an assessment of the missed test on equipment operability. This assessment will consider the effect on a margin of safety (equipment operability) . Should the component be inoperable, the Technical Specifications provide actions to ensure that the margin of safety is protected . The proposed change also eliminates a statement that nothing in the ASME Code should be construed to supersede the requirements of any TS . The NRC has determined that statement to be incorrect. However, elimination of the statement will have no effect on plant operation or safety.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above , SNC concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50 .92(c) ,

and , accordingly , a finding of "no significant hazards consideration" is justified.

4.0 ENVIRONMENTAL EVALUATION The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20 , or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration , (ii) a significant change in the types or a significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure .

Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51 .22(c)(9). Therefore, pursuant to 10 CFR 51 ,22(b) , no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.

E1 -5

Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, "TS lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing," and to Request an Alternative to the ASME Code Enclosure 2 FNP, HNP, and VEGP Technical Specification Marked Up Pages

1.1 Definitions ENGIN EERED SAFETY The ESF RESPONSE TIME shall t>e that time inte rval from FEATURE (ESF) RESPONS E w hen the monitored parameter exceeds its ESF actuation TIM E .setpoint at th e chann el sensor until th e ESF equipment is

,capable-of performing its safetyfunction (i. e., the valv es traveI to their required pas iti ons. pump dis charge press ure.s reach th eir requiredvalu es, etc.). Times shall include diesel generator starting andsequence loading delays , where applicable . The response time may be measured by means of any series of sequential,overlapping.,ortotal steps so that the entire response time is measured In lieu of mea.surement. response time may be verifiedfor selected oomponents providedthatthe components andthe methodology f or verification have been previously revie'!Ned and approved by the NRC .

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAG E, such as that from pump.seals or valve packing {except reactor coolant pump (RCP) .seal water injection or leakoff). that is captured and conductedtocollection systems or a sump or collecting tan k;

2. LEAKAGE into the containment atmospherefrom sources that are both specifically located and know n either not to interfere w ith th e operation of leakage detection systems or not to be pressure boundary LEAKAGE; or

3. Reactor Coolant System (RCS) LEAKAG E thmugh a steam generator (SG) to the Seconda ry System ;

b. Unidentified LEAKAG E All LEAKAG E ( except RC P seal w ater injection or leakoff)that is not identified LEAKAG E; INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f).

(continued)

Farley Units 1 and 2 1.1-3 Amendment No . 1-4-9 (Un it 1)

Amendment No. ttt- (Un it 2 )

Pressurizer Safety Valves 3-4.10 SURV EILLANCE REQUIRE MENTS SURVEILLANCE FREQU ENCY S R 3.4.1:0.1 V erify each pres surizer safety v alv e is OPERABLE in accordance with the IAser.*iee TestiA§ PFO§Faffl.

Followi ng testing, lift settings shall be within :t 1%.

Farley Units 1 and 2 3-4.10-2 Amendment No. 14&- (Unit 1)

Amendment No. 1 (Unit 2)

LTOP System 3.4.12

~ St.JRVEl lJANCE REQUIRE MENfTS SURVEILLANCE FREQUENCY SR 3.4.12.1: V erify a maximum of one charging pu mp is In accordance with capable of inj ecting into the RCS when one or more the Surveillance RCS cold legs is 5: 180F. Frequency Control Program SR 3.4.12.2 V erify a maxi mum of two charging pumps are In accordance with capable of inj ecting into the RCS when all RCS c ol d the Surveillance legs are> 180F. Frequen cy Control Program SR 3.4.12.3 V erify each accumulator is isolated. In accordance with the S urveillance Frequency Control Program SR 3.4.12.4 V eri fy RHR suction isolation valv es are op en for each In accordance with requ ired RHR suction relief v alv e. the Surv eill ance f requency Control Program SR 3.4.12.5 -NOTE------ ------ - --

Only required to be performed when complying with LOO 3.4.12.b.

V erify RCS v ent~ 2.85 square inches open . ln accordance with the Surveillance Frequency Control Program SR 3.4.12.'6 V erify each requ ired RHR suction rel ief v alv e ln accordance with setpoint. the frrnel"1'iee TestiR§ Pffi§ffim

"?!

AND In accordance with

(:sERVICE TESTING PROGRAM the Surveillance Frequency Cont rol Program c:

Farley Units 1 and 2 3.4.12-4 A mendment No. 'ffli3-(Unit 1)

A mendment No. 1-89-(Unit 2)

ECCS-Operating 3_5_2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3_5_2_1 - - - -- ----- - - NOTE - - - -- - -- - - --

Only required to be performed: fo rv alv es 8132A and 81328 when Centrifugal Charging1Pu mp A is inoperable _

V erify the followin9 v alv e*s are in t he listed p osition In accordance with with powerto the v alv e op erator re mov ed_ the Surveillance Frequen cy Control Nu mber Position Function Program 8884, 8886 Close d Centrifugal Charging Pump to IRCS Hot Leg 8132A, 81328 Open Centri fugal Charging Pump discharge isolat ion 8889 Close d RHR to RCS Hot Leg [nj ection SR 35-2-2 V erify each ECCS manual, power op erated, and In accordance with automatic v alve in the flow path, t hat is not loc ed. the Surveillance sealed, or otherwise secured in p osition, is in t he Frequency Control correct position _ Program SR 3-5.2-3 V erify each ECCS pu mp' s dev elop ed he*a d at the test In accordance with flow point is greater t han or equal to the re quire d the lflserviee dev eloped head_ Te3ting, Program 1

11 SR 3-5.2-4 V erify each ECCS automatic v alve in t he flow path Ln accordance with t hat is not locked, seale d, or othe rwi se secure d in the Surveillance position, actuates to the correct position on an actual Frequency Control or simulated actuation signal. Program

~RVICE TESTING PROG-:0 Farley Units 1 and 2 3_5_2-2 A mend ment No _ +as- (Unit 1)

A mendment No _ "IB6- (Unit 2}

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUI RE MENTS SURVEI LLANCE FREQU ENCY SR 3_6_3_3 NOTES-------- - - - -- --

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means _

2. The blind flang,e on the fuel transfer canal flange is only required to be verified closed after each draining, of the canal _

Verify each containment isolation manual valve and Prior to enterin9 blind flange that is located inside containment and MODE 4 from not locked, sealed, or ot herwise secured and MODE 5 if not required to be closed during accident conditions is performed within closed , except for containment isolation v alves that the previous are open under administrative controls _ 92 days SR 3.6.3.4 Verify the isolation li me of each power operated or automatic containment isolation valve in the -fSf-Progran1 is within li mits _

SR 3.6.3-5 Perfo leakage rate testing for containment n accordance with penet tions containing contain ment purge v alv es the Surveillance with re *1ient seals _ Frequency Control Program AND Within 92 days after openingi the v alve SR 3_6_3_6 Verify each automatic containment isolation v alv e In accordance with that is not locked, sealed or otherwise secured in the Surveillance position, act uates to the isolation position on an Frequency Control actual or simu lated actuation signal. Program Farley Units 1 and 2 3 6.3-6 Amendment No _ te5- (Unit 1)

Amendment No 1~ (Unit 2)

Containment Spray and Cooling Systems

- 3.6.6

~ERVICE TESTING PROGRAM SU RVEILlANCE REQUIREMENTS \

SURVEILLANCE

\ FREQUENCY SR 3.6.6.4 V erify each containmen~ s~ray pu mp' s dev eloped \ In accordance with head at the flow t est point 1s greaterthan or equal t o , J the IAseF't'iee the require d dev eloped head _ +estiR§ PFe§F<Ht:t SR 3.6.6.5 V erify each automatic containment spray valv e in the In accordance with flow path that is not lo ck ed , sealed, or otherwise the Surveillance secure di in position , actuates to the correct position Frequency Control on an actual or si mulated actuation signal. Program SR 3.6.6.6 Verify each cont ainment spray pump starts In accordance with automatically on an actual or simulated actuation the Surveillance signal. Frequency Control Program SR 3.6.6.7 V erify each containment cooling train starts In accordance with aut omatically on an act ual or simulated actuation the Surveillance signal. Frequency Control Program SR 3.6.6.8 Verify each spray nozzle is unobstructed. In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.6.6-3 Amendment No. 1 (Unit 1)

Amendment No. 100- (Unit 2)

MSSV s 3.7.1 ACTI ONS CON DITT ON REQU IRED ACTIO N COMPLETION TIME

8. (continued) 8 .2 -NOTE- - - - --

Only required in MODE 1.

Reduce the Power Range 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Neutron Flux-High reactor trip setpoint to less than or equal to the Maximum Allowable % RTP specified in Table 3. 7.1:-1 forthe number of OPERABLE MSSV s.

C. Requ ired Action and c .11 Be in MOD E 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Ti me not met. AND C.2 Be in MOD E 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR One or more steam generators with ~ 4 MSSV s inoperable .

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQU ENCY SR 3.7.1.1 -NOTE- - - - - - - - -----

Only required to be performed in MODES 1 and 2.

V erify each required MSSV Ii.ft setpoint per Table In accordance with

3. 7.1-2 in accordance with the l'RsePv"ice Testing th e ll'lserviee Program. Following testing , lift setting shall be within Testing Progran1

+/-1:%.

Farl ey Units 1 and 2 3 7.1-2 A mendment No. T46- (Unit 1)

A mendment No 1-3-t-- (Unit 2)

MS IVs 3.7_2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E_ One or more steam lines E_1i Verify one MSIV closed in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with two MSIV s affected steam line _

inoperable in MODE 2 AND or3 _

Once per 7 day s thereafter F_ Required Action and f _1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition D or E AND not met F-2 Be in MODE 4_ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SU RVEILLANCE REQUIREMENTS SllRVEIU.ANCE FREQUENCY SR 3_7_2_1 NOTE-- - - -- - - - - - - - -

Only require d to be performed in MODES 1 and 2.

V erify closure ti me of each MSIV is :5 7 seconds _ In accordance with th e IRserviee TesliRg, PFOgfa.ffi Farley Units 1 and 2 3-7.2-2 Amendment No _ 14&- (Unit 1)

Amendment No 1-:ff- (Unit 2)

Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS OONDil!ON REQUIRED ACTION COMPLETI'. ON TIME C. One or more MFIRV C.1 Close or isolate bypass 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by pass v alv es v alv e.

inop erable.

AND C.2 V erify bypass valv e is dosed Once p er 7 day s or isolated.

0 . Two v alv es in the same D.1 Isolate affecte d flow path . 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow path ino perable .

E. Required Action an d E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 1

associated Completion Time not met SIU RVEll lANCE REQUIREMENTS SU RVEILLANCE FREQUENCY SR 3.7.3.11 V erify the closure ti me of each Main FW Stop Valv e, In accordance with MFIRV, and associate d by pass valve is in accordance t he ll'lsel"o'iee with the ti me requ ire ment in the IMef'o'iee Testil'lg. Testil'lg Program.

~

Farley Units 1 and 2 3.7.3-2 Amendment No. 146- (Unit 1)

Amendment No. Bl- (Unit 2)

AFW Sy ste m 3_7_5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7-5.2 -NOTE- - - - - ---- -- - - --

Not requ ired to be performed for the turbine driv en AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after~ 1005 psig in the steam generator.

V eri fy the dev eloped head of each AFW pump at the flow test point is greaterthan or equal to the required dev elop ed he ad_

SR 3-7_5_3 Verify each AFW automatic valve that is not locked, In accordance sealed, or otherwise secured in position. actuates to with the the correct position on an actual or simulated Surveillance actuation signal. Frequen cy Control Program SR 3_7_5_4 NOTE - - - - - - - - - - -- - --

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after~ 1005 psig in the steam generator.

Veri fy each AFW pu mp starts automatically on an In accordance actual or simulated actuation signal. with the Surveillance Frequency Control Program SR 3.7-5.5 V erify the turbine driven AFW pump steam admission l'n accordance valv es open when air is supplied fro m their respective with the air accumulators. Surv eillance Frequency Control Program Farley Units 1 and 2 3.7-5-3 A mendment No TS5- (Unit 1)

Amendment No _ too- (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Reactor Coolant Pu mp Flywheel l'nspection Program (continued)

b. A surface examination (magnetic particle and/or liqu id penetrant) of exposed surfaces of the disassembled flywheel.

The provisions of SR 3.0.2 and SR 3.0.J. are applicable to the Reactor Coolant Pu mp Flywheel Inspection Program.

~

Not Used J

5.5.8 --+iln~s~E!>f'f\.ttiif" e,..e-tc T~e~stm in wgr IP

-'ff fOW'9tt';ffijt1ffiFfl1-This program provides controls for inservice testing of ASME Code Class 1, 2, a 3 co mponents . The program shall include the following 1 1

a. , sting frequencies specified in Section XI of theASME Boiler a Pre ure Vessel Code and applicable Addenda as foll ows:

ASM E B

er and Pressure V essel Cod nd applicable Ad da termi nology for quired Frequencies inservice testing for performing in service activities testing activities Weekly At least once per 7 days Monthly At least once per 31 day s Quarterly or ev ery 3 months At least once per 92 days Sem iannually or every 6 onths At least once per184 day s Ev ery 9 months At least once per276 day s Y early or annually

east once per 366 days Bienn ially orev 2 years Al le t once per 731 day s

b. The provi *ons of SR 3.0.2 are appli cable to the abov e guired f requ cies for performing inservice testing activities;

c. provisions of SR 3.0.3 are applicable to in service testing ac

Nothing in the ASME Boiler an d Pressure Vessel Code shall be cons to supersede the requirement s of any TS.

5.5.9 Steam Generator (SG} Program A Steam Generator Program shall be establishe d and implemented to ensure that SGtube integrity is maintained. tn add1tion, the Steam Generator Program shall include the followi ng1:

a. Provi sions for condition monitoring assessments. Condition monitoring (continued)

Farley Units 1 and 2 5.5-5 Amendment No. 1-9Z-(Unit 1)

Amendment No. ffit}-(Unit 2)

Definitions 1.1 The INSERVICE TESTING PROGRAM is the licensee 1.11 Definitions (continued) program that fulfills the requirements of 10 CFR 50 .55a(f) .

END O F CYCLE The EOC-RPT SYSTEM RESPONS E TIME shall be that time interval RECllRCUl.ATION from initial signal generation by the associated turbine* stop v alve limit PUMP TRIP switch or from when the turbine control valv e hy draulic control (EOC-RPT) oil pressure drops below the pressure switch setpoint to complete SYSTEM suppression of the electric arc between the fully open contacts ofthe RESPONS E TIM E recirculation pu mp circuit breaker. The respon se ti me may be measured by mean s of any series of se quential , ov erlapping,, or total steps so that the entire re sponse ti me is measured.

LEAKAG E shall be :

a. Identified LEAKAG E 1i. LEAKAG E into the drywell, such as that fro m pump seals or valv e packing, that is captured and conducted to a sump or collecting tan k; or

2. LEAKAGE into the drywell atmosphere fro m source s that are both specifically located and known either not t o INSERVICE interfere with the operation of leakag,e det ection sy stems or TESTING not to be pressure boundary LEAKAG E; PROGRAM b_ Unidentified LEAKAGE All LEAKAG E into t he drywel l that is not identified LEAKAGE; c_ Total LEAKAGE Sum of the identified and unidentified LEAKAG E; d_ Pressure Boundary LEAKAG E LEAKAGE through a nonisolable fault in a Reactor Cool ant Syst em (RCS} component body , pipe wall. or v essel wall.

LI NEAR HEAT LIN EAR HEAT GENERATION RATE (LHGR} shall be the powerg:eneration

G ENERAl!ON in an arbitrary length of f uel rod, usually six inches . ll is the integral of the RATE heat flux ov er the heat transfer area associated with the unit length _

l.cOG!C SYSTE M A LOG[C SYSTEM FUNCTIONAL TEST shall be a test o f all FUNCTIOl\Y\l required logic components (i.e., all require d! relay s an d contacts , trip TEST units. solid state logic elements, etc.) of a logic circuit, from as close to the sensor as practicable up to, but not including, the actu ated device, to v erify OPE RABILlifY_ Th e LOGIC SYSTE M FUNCTIONAL TEST may be performed by means of any series of sequential, ov erlapping\ or total sy stem steps so that the entire log ic sy ste m is t est ed _

(continued)

HATCH UNIT 1 1.1-3 Amendment No. ~

SLC Syste m

/.:~--

\_'NSERVICE TESTING PROGRAM

~ 3. 1 . 7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.7 V erify each pump develops a flow rate:<! 41 .2 gpm at a discharge pressure~ 1232 psig.

In accordance with the lnservice j

Testing Program SR 3.1.7.8 Verify flow through one SLC subsy ste m fro m pump In accordance with into reactor pressure vessel. the Surveillance Fr!)quency Control Program SR 3.1.7.9 Verify all heat traced piping betw een storage tank In accordance with and pump suction is unblocked. the Surveillance Frequency Control Program Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after pump suction piping te mperature is restored with in the Region A limits of Figure 3.1.7-2 SR 3.1.7.1'0 Verify sodium pentaborate enrichment is Prior to addition to

~ 60.0 ato m percent B-10. SLC tank HATCH UNIT 1 3.1-20 Amendment No. ~

S/ RV s 3.4.3 SURV EILLANCE REQUIREMENTS SURVEI LLANCE FREQU ENCY S R 3.4.3.1 Verify the safety f unction lift setpoints of the S/ RV s In accordance with are as follows: the l'r-,seroo ice Te!lting Progra:n1 Number of Setpoint S/RV s {Qfilg) 11 1150< +/- 34.5 Following testing, lift settings shall be within+/- 1%..

HATCH UNIT 1 3 4-6 A mend ment No . ~

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS continued SURVElllANCE FREQU ENCY SR 3.5.1.6 -NOTE-- - -- - -- - - --

Only required to be performed prior to entering:

MODE 2 fro m MODE 3 or4, when in MODE 4

> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

V erify each recirculation pump discharge v alv e In accordance with cycles through one complete cycle of full trav el or the Surveillance is de-energ,ized in the closed position . Frequency Control Program SR 3.5.1.7 V erify the followi ng EGGS pu mps develop the specified flow rate ag ainst a system head 1

corresponding to the specified reactor pressure.

SYSTEM HEAD CORRESPONDING NO . O F TOAREACTOR SYSTEM FLOW RATE PU MPS PRESSURE O F cs 2 . 4250 g:pm 1 ~ 113 psig LPCI 2 17 ,000 gpm 2 2 20 psig SR 3.5.1.8 -NOTE- - - - - -- -----

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor.steam pressure and flow are adequate to perform the test V erify , with reactor pressure~ 1!058 psig and In aocordance with

~ 920 psig, the HPCI pump can develop a flow the Surveillance rat e ~ 4250 gpm against a system head Frequency Control corresponding to reactor pressure . Program (continued)

HATCH UNIT 1 3.5-4 Amendment No ....26.6.

ECCS - Shutdown 3_5_2 SURVEILLANCE REQUIREMEN!fS continue SURVEILLANCE FREQUENCY SR 3_5_2-3 V erify. for each required ECCS injection/ spray In accordance with subsy stem, the piping is filled with water fro m the the Surveillance pump discharge valv e to the injection valv e. Freque ncy Control Program SR 3.5.2.4 -NOTE - - - - - - - -- - -

One lPCI subsy stem may be considered OPERABLE during: align ment and operation for decay heat re mov al if capable of being manually realigned and not otherwise inoperable.

V erify each required ECCS inj ection/spray l'n accordance with subsy ste m manual, power operated, and t he Surveillance automatic valv e in the flow path, that is not locked, Frequen cy Control sealed, or otherwise secured in position, is in the Program correct position .

SR 3.5.2.5 V erify each required ECCS pump dev elops the In accordance with specified flow rate against a system head the lnservice corresponding to the specified reactor pressure . lestiAg PFOgram SYSTEM HEAD CORRESPONDING NO.OF TOA.REACTOR SYSTEM FLOW RATE PU MPS PRESSURE O F cs 24.250gpm 1 "'113 psig LPCI 2 7700gpm 1 2 .20psig SR 3.5.2.6 NOTE- - - - - - - - - - - --

V essel inj ection/ spray may be excluded.

V erify each required EOCS inj ection/ spray l'n accordance with subsy stem actuates on an actual or si mulated the Surveillance automatic initiation signal. Frequency Control Program INSERVICE TESTING PROGRAM HATCH UNIT 1 3.5-8 Amendment No.-:2£&

PCIVs 3.6.1.3 SURV EIU.ANCE REQUIREMENTS continued SURVEILLANCE FREQU ENCY SR 3.6.1.3.2. NOTES-- - -- - - - - - -

1. Valv es and blind flanges in high radiation areas may be v erified by use of administrativ e means.

2. Not required to be met for PCIV s that are open under administrativ e contro ls.

V erify each pri mary containment isolation manual In accordance with v alv e and bl ind flange that is located outs ide the Surveillance pri mary containment and is required to be closed Frequency Control during accident conditions is closed. Program SR 3.6.1.3.3 NOTES- - - -- - - - - - -

1. Valv es and blind flanges in high radiation areas may be v erified by use of administrativ e means .

2. Not requ ired to be met for PCIVs that are open under administrativ e controls .

V erify each primary contain ment manual isolation Priorto entering v alv e and blind flange that is located inside MOD E 2 or 3 fro m primary contain ment and is required to be closed MOD E 4 if pri mary during accident cond itions is closed. contain ment was de-inerted while in MOD E 4, if not perfo rmed within. the prev ious 92 day s SR 3.6.1.3.4 V erify continuity of the trav ersing in core probe In accordance with (flP) shear isolation v alv e explosiv e charge. the Surveillance Frequency Control Program SR 3.6.1.3.5 V erify the isolation ti me of each power operated l'n accordance with and each automatic PCIV , except for MSIV s, is the IRseFViee within limits. TestiA§ PFO§Fam (continued)

INSERVICE TESTING PROGRA HATCH UNIT 1 3.S-11 A mendment No. Z6'6-

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1'.3.6 V erify the isolation time of each MSIV is rn accordance with

~ 3 seconds and~ 5 seconds . the ll'lse!'Viee festing Program 0NSERVICE TESTING PROGRAM\-

SR 3.6.1.3.7 V erify each auto matic PCIV , excluding EFCV s, In accordance with actuates to the isolation position on an actual or the Surveillance simulated isolation signal. Frequen cy Control Program SR 3.6.1.3.8 . V erify each reactor instru mentation line EFCV (of In accordance with a representative sample) actuates to restrict flow the Surveillance to within limits. Frequency Control Program SR 3.6.1.3.9 Remov e and test the explosiv e squib fro m each In accordance with shear isolation valv e of the TIP sy ste m. the Surve illance Frequency Control Program SR 3.6.1.3.10 V erify co mbined MSl< V leakage rate for all four In accordance with main steam lines is~ 100 scfh when tested at the Primary

~ 28.0 psig and < 50.8 psig . Contain ment Leakage Rate OR Testing Program V erify co mbined MSIV leakage rat e for all four main steam lines is~ 1i44 scfh when t este d at

~ 50.8 psig .

SR 3.6.1.3.11 Deleted SR 3.6.1.3.12 Cycle each 18 inch ex cess flow isolation damper In accordance with to the fully closed and full y open position _ the Surve illance Frequency Control Program SR 3.6.1.3.13 V erify the combined leakage rat e for all secondary In accordance with containment bypass leakage paths is~ 0.02 La the Primary when pressurized to~ Pa. Contain ment Leakage Rate Testing Program HATCH UNIT 1 3 6-12 Amendment No.--260

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6. 1.7 ACTI:ONS (continued)

CONDITION IREQUllRED ACTl:ON COMPLETION TlME E. Required Acti on and E.1 Be in MOD E 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associat ed Co mplet ion Ti me not met Be in MOD E 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURV EILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.1 NOTES--- - - - - - - -

1. Not require d to be met for vacuu m breakers lha1 are open during Surv eillances.

2. to Not requ ire di be met for v acuu m breakers open when performing their int en ded function .

V erify each v acuu m breaker is dose d. In accordance with t he Survei llance Frequency Control Program SR 3.6.1. 7.2 Perfo rm a fu nctional test of each v acuu m breaker. l'n accordance wit h the lnservise Testing Pmgr:am SR 3.6.1.7.3 V eri fy the opening setpoint of each v acuu m l'n accordance wit h breaker is .~ 0.5 psi d. t he Su rv eillance Frequency Cont rol Program HATCH UNIT 1 3.6-18 Amendment No."'Z"6'6"

RHR Suppression Pool Cooling 3.6.2.3 SURVEIL LANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.i6.2.3.2 Verify each required RHR pump dev elops a flow In accordance with rate ~ 7700 gpm through the associated heat exchanger while operating: in the suppression pool t-tnln;ttTTn"'P'TT"Tnr::nn-cooling mode .

INSERVICE TESTING PROGRAM HATCH UNIT 1 3 . 6~26 A mendment No . ~

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5_5 Component Cyclic or Transient limit This program provides controls to track FSAR Section 4.2, cyclic and transient occurrences , to ensure that reactor coolant pressure* boundary components are maintained within the design limits_

5.5.6 lnserviee Tes~i A § PFO§FBlfl

is program provides controls for in service testing of A SME Code Class 1, 2, co mponents includin g applicable supports _

a_ Te ing frequencies specified in Section XI of the ASME Baile Pres e V essel Code and applicable Addenda are as foll ASME Baile nd Pressure V essel Co de a Applicable 1

Required requencies Addenda Termino for for Pe arming lnservice lnservice Testin Te n Activities Weekly 7 day s Monthly 31r day s Quarterly or ev ery 3 months At least once per 92 days Semiannually or ev ery 6 nths t least once per 1i84 day s Yearly or.annually A , ast once per366 day s b_ The provisions *SR 3.0.2 are appli cable t o the performing i erv ice t estingi activiti es ;

c_ The P, vi sions ofSRJ..0.3 are applicable to inservice test1 an Nothing' in the ASM E Boiler and Pressure V es.sel Code shall be con to supersede the requirem ents of any Technical Specification _

5.5_7 V entilation Filter Testing Program (VFliP)

The VRP will establish the required testin9 of Engi neered Safety Feature (ESF) filter v entilation sy ste ms at the frequencies specified in Regulatory Guide 1.-52, Revision 2, Sect.ions CSc and C.5.d, or: 1) after any structural maintenance on the HEPA filterorcharcoal adsorberhousings, 2) following painting, fire or chemical release in any v entilation zone communicating with the sy stem, or 3) after ev ery 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation.

(continued)

HATCH UNIT 1 5.0-10 Amendment No ~

Definitions 1_1 11_1 Definitions (continued)

EMERGENCY The ECCS RESPONSE TIME shall be that time interval from when CORE COOLING the monitored parameter exceeds its ECCS initiation setpoint at the SYSTE M (ECCS) channel sensoruntil the ECCS equipment is capable of performing RE SPONSE its safety function (i .e., the valves travel to their required positions, TlME pump discharge pressures reach their required values , etc.). Times shall include diesel generator starting and sequence loading delays , where applicable_ The* response time may be measured by means of any series of sequential, ov erlapping, or total steps so that the entire response time is measured_

END OF CYCLE The EOC-RPT SYSTEM RESPONS E TIM E shall be that time interval RECIRCULATION from initial signal generation by the associated turbine stop valve limit PUMP TRIP switch or from when the turbine control valve hydraulic control oil (EOC-RP1) pressure drops below the pressure switch setpoint to complete SYSTEM suppression of the electric arc between the fully open contacts of the RESPONSE TIME recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured_

ISOLATION The ISOl..ATfON! SYSTEM RESPONSE TIM E shall be that time interval SYSTEM from when the monitored' parameter exceeds its isolation initiation RESPONSE TIME setpoint atthe channel sensor until the isolation valves travel to their required positions . Times shall include diesel generator starting and sequence load'ingi delays, where applicable . The response time may be measured by means of any series of sequential , overlapping', or total steps so that the entire response time is measured_

LEAKAG E LEAKAG E shall be :

a. Identified LEAKAGE

1. LEAKAGE into the drywell , such as that from pump seals or v alve pack.ing', that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the <lrywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b. Unidentified LEAKAG E All LEAKAGE into the drywell that is not identified LEAKAGE; INSERVICE The INSERVICE TESTING PROGRAM is the licensee TESTING program that fulfills the requirements of 10 CFR 50.55a(f).

PROGRAM (continue~

HATCH UNIT 2 1.1-3 Amendment No. 4+&-

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS continued SURVElllAN:CE FREQUENCY SR 3.116 V erify each SILC subsystem manual and power l'n accordance with operated valve in the flow path that is not locked, the Surveillance seale d, or otherwise secured in position is in the Frequency Control correct position, or can be aligned to the correct Program position _

SR 3.1.7.7 V erify e.aoh pump develops a flow rate~ 41 .2 gpm rn accordance at.a discharg.e pressure~ 1232 psig _ With the rRsef'u'ice Test.ing Pro gran1 SR 3.11_7_8 V erify flow through one SLC subsystem from pump In accordance with into reactor pressure v essel. the Surveill ance Frequency Control Program SR 3_1_7_ 9 V erify all heat traced piping between storage tan l'n accordance with and pump suction is unblocked. t he Surveillance Frequency Control Program Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after pump suction piping t emperatu re is restored within the Region A li mits of Figure J _1_1~2 SR 3.1.7.110 V erify sodium pentaborate enrichment is Priorto addition to

~ 60.0 ato m percent B-10.

1 SIL:C tan k HATCH UNIT 2 3.1-19 Amendment No.-21tt

S/RV s 3.4.3 SURV EILLANCE REQUIREMENTS SURV EILLANCE FREQUENCY SR 3.4.3.1 V eri fy the safety function lift setpoints of the Sl RVs are as follows:

Number of Setpoint S/ RV s ~

11 1150 +/- 34.5 Followi ng testing, lift settings shall be with in +/- 1%.

HATCH UNIT 2 3 4-6 A mendment No::-7!49

ECCS - Operating 3.5.1 SURV EILLANCE REQUIREMENTS continued SURVEILlANCE FREQUENCY SR 3.5.1.6 - - - -NOTE--- - - -- - -- -

Only requ ired to be performed prior to entering' MOD E 2 fro m MODE 3 or4, when in MOD E 4

> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

V erify each recirculation pump discharge v alv e In accordance with cy cles through one co mplete cycle of fu ll trav el or the Surve illance is de-energized in the closed position. Frequency Control Program SR 3.5.11.7 V erify the following ECCS pu mps dev elop the fn accordan ce with sp ecified fl ow rate against a sy ste m head the IFtservice correspond ing to the specified reactor pressu re. Testing Program SYSTEM HEAD CORRESPONDING NO . OF TOAREACTOR SYSTEM FLOW RATE PU MPS PRESSURE OF cs 2 4250 gpm 1 2113 psig LPCI 2 17,000 gpm 2 2 20 ps ig, SR 3.5.1<.8 NOTE- - - - - - - - --- -

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

V erify , with reactor pressures 1058 p sigi and In accordance with

~ 920 psig, the HPCI pump can dev elop a flow the Surveillance rate~ 4250 gpm against a sy stem head Frequency Control corres ponding to reactor pressure. Program

{continued)

INSERVICE TESTING PROGRAM HATCH UNIT 2 3.5-4 A mend ment No ~

EGGS - Shutdown 3.5-2 SURV EILLANCE REQUIREMENTS continue ,

SURVEILl!.ANCE FREQUENCY SR 3.5.2.3 V erify , for each required EOCS inj ection/ spray In accordance with subsystem, the piping is filled with water fro m the the Surveillance pump discharge v alv e to the inj ection v alv e. frequency Control Program SR 3.5.2..4 NOTE----- - - - - - - -

One LPCI' subsy ste m may be considered OPERABLE during, al ignment anp operation for decay heat removal if capable of being. manually realigned and not otherwise inoperable .

Verify each required ECCS inj ection/ spray In accordance with subsyste m manual , power operated, and the Surveillance automatic v alv e in the flow path, that is not locked, Frequency Control sealed, or otherwise secured in position, is in the Program correct position.

SR 3.5.2.5 Verify each required EGGS pump develops the specified flow rate against a system head corresponding to the specified reactor pressure.

SYSTEM HEAD CORRESPONDING NO . OF TO A. REACTOR SYSTEM FLOW RATE PU MPS PRESSURE O F cs :=: 4250gpm 1 2 113 psig, LPCI ::: 7700gpm 1 :=: 20psig SR 3.5.2.'6 NOTE------------

Vessel injection/ spray may be exclude d!.

V erify each required EGGS inj ection/ spray In accordance with subsystem actuates on an actual or simu lated the Surveillance automatic initiation signal. Frequency Control Program ERVICE T~ PROGRA!?1 HATCH UNIT 2 3 . 5~9 A mendment No .....z.-ttr

PCIV s 3.6.1.3 SURV EIU.ANCE REQUIREME NTS (continued~

SURVEILLANCE FREQUENCY SR 3.6.1.3.2 - - - - - - -----NOTES - - - - - - - - - - -

1. V alv es and blin d flang,es in high radiation areas may be v erifie d by use of administrativ e means .

2. Not required to be met for PCIV s that are open un der administrativ e controls.

V erify each pri mary containment isolation manual In accordance with v alv e and blind flang.e t hat is located outside the Surveillance pri mary contain ment and is required to be closed Frequency Control during accident condit ions is close d. Program SR 3.6.1.3.3 - - - - - - -*- ---NOTES-----------

1:. Valv es and blind flanges in high radiat ion areas may be v erified by use of administrativ e means.

2. Not required to be met for PCIV s that are open un der administrativ e controls .

V erify each pri mary contain ment manual isolation Priorto entering valv e and bl ind flange that is located inside MOD E 2 or3 from primary contain ment and is require d to be closed MODE 4 if primary during accident conditions is close d. contain ment was de-inerted while in MODE 4, if not performed within the prev ious 92 day s SR 3.6.1.3.4 Verify continuity ofthe trav ersing in core probe In accordance wit h (TIP) shear isolation valv e explosiv e charge. the Surveillance Frequency Control Program SR 3.6.1.3.5 Verify the isolation time of each power operated In accordance wit h and each automat ic PCIV, e*x cept for MSl,V s, is the ~n se rv i ce within limit s.

(continued)

~ERVICE TESTING PROGRAM HATCH UNIT 2 3.S-11 A mendment No.--2ttt

PCIV s 3.6 1.3 SURVEILLANCE REQUIRE MENiTS (continued)

SURVEIULANCE FREQUENCY SR 3.6.1.3.6 Verify the isolation time of each MSIV is In accordance with

~ 3 seconds and~ 5 seconds _ the lnse Niee l INSERVICE TESTING PROGRAM T

. - n .

~ -~

U. 111 SR 3.6.1.3.7 Verify each auto matic PCIV , excluding EFCVs , In accordance with actuates to the isolation position on an actual or the Surveillance si mulated isolation signal. Frequency Control Program SR 3.6.1.3.8 V erify each reactor instru mentation line EFCV (of In accordance with a representativ e sample) actuates to restrict flow the Surveillance to within limits. Frequency Control Program SR 3.6.1.3.9 Remov e and test the explosive squib fro m each In accordance with shear isolation v alv e of the TI P system. the Surveillance Frequency Control Program SR 3.6.1.3.10 Verify the co mbined leakage rate for all In accordance with secondary containment bypass leakage paths is the Primary

~ 0.02 La when pressurized to~ Pa. Containment Leakage Rate Testing' Program SR 3.6.1.3.11 V erify combined MSIV leakage rate for all four In accordance with main steam lines is~ 1'00 scfh when tested at :2: the Primary 28.8 psig and < 47.3 psig. Containment Leakage Rate OR Testing Program Verify combined MSIV leakage rate for all four main steam lines is~ 144 scfh when te sted at :2:

47_3 psig_

SR 3.6.1.3.12 Deleted SR 3. 6. 1 . 3. 1~ 3 Cycle each 18 inch excess flow isol ation damper In accordance with to the fully dosed and fully open position _ the Surveillance Frequency Control Program HATCH UNIT 2 3 6-12 A mendment No:-Z-ffi

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6. 1.7 ACTIONS continued CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Co mpletion Time not met AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURV EILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.1, NOTES - - - - - -- -- -

1. Not required to be met for vacuu m breakers that are open during Su rv eillances .

2. Not required to be met for vacuu m brea ers open when perfo rming their intended funct ion .

V erify each v acuum breaker is closed. In accordance with the Surveillance Frequency Control Program SR 3.6.1.7.2 Perfo rm a functional test of each vacuu m breaker. In accordance with t he IAservice Testing PFOgr:am SR 3.6.11.7.3 V erify the open ing setpoint of each vacuum l'n accordance with breaker is .s: 0.5 psid. the Surveillance frequency Control Program INSERVICE TESTING PROGRAM HATCH UNIT 2 3.6-18 Amendment No.-2ttT

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQU ENCY SR 3.6.2.3.2 V erify each required RIHR pump dev elops a flow In accordance with rate ~ noo gpm through the associ ated heat the lnservice ex changer while operating in the suppression pool Testin~l PFogram cool ing mode .

INSERVICE TESTING PROGRAM HATCH UNIT 2 3.6-26 Amendment No -t3'5-

Programs and Manuals 5.5 5-5 Programs and Manuals (continued) 5-5.5 Component Cyclic or Transient Limit This program provides controls to track FSAR Section 5.2, cyclic and transient occurrences , to ensure that reactor coolant pressure boundary components are maintained within the design limits.

5.5.6 l'nse rvi ce lesting Pro gram is program provides controls for inservice testing of ASME Code Class 1, 2, 3 co mponents includingi applicable supports.

a_ tin9 frequencies specified in Section XI of the ASME Boil Pres re Vessel Code and appl icable Addenda are as foll ASME Boi and Pressure V essel Code a Applicable Require requencies Addenda Termino y for for P, arming In service lnservice Testin Ac

lies T tin Activities Weekly At least once per 7 days Monthly At least once per 31i days Quarterly or ev ery 3 month At least once per 92 days Semiannually or every 6 onths At least once per 184 days Yearly orannually east once per 366 day s

b. The provisions SR 3.0.2 are applicable to the performing

service testing activities ;

Nothing in the ASME Boiler and Pressure Vessel Code shall be con to supersede ihe requirements of any Technical Specification.

5.5. 7 Ventilation Filter Testingi Pro gram (VFTP)

The VFTP will establish the required testing of Engineered Saf ety Feature (ESF) filter ventilation syste ms at the frequencies specified in Reg,ulafory Guide 1.52, Revision 2, Sections C.5.c and C.5.d, or: 1} after any structural maintenance on the HEPA filter or charcoal adsorber housings, 2) following painting , fire or chemical release in any v entilation zone communicatingi with the system, or 3) after ev ery 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation .

(continued)

HATCH UNIT 2 5.0-10 Amendment No. -+74-

Definitions 1_1 1_1 Defin itions (continued)

E - AVERAGE E shall be the average (weighted in proportion to DISINTEGRATION ENERGY the* concentration of each radionuclide in the reactorcoolant at the time of sampling) oHhe sum of the av erage beta and gamma energies per disintegration (i n MeV) for isotopes, other than iodines , with half liv es> 14 minutes, making up at least '95% of the total noniod'ine activ ity in the coolant ENGINEERED SAFElY The ESF RESPONS E TIME shall be that time FEATURE (ESF) RESPONS E interval from when the monitored parameter ex ceeds its TIME ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e.,

the v alves trav el to their require d positions , pump discharge pressures reach their required values , etc.). Times shall include diesel generator starting and sequence loading:

delay s, where applicable . The re*sponse ti me may be measured by means of any series of sequential , overlapping, ortotal steps so that the entire response time is measured.

In lieu of measurement, response time may be verified for select ed components provi dedthat the components and the methodology for verification hav e been previously review ed and approved by the NRC.

LEAKAGE LEAKAGE shall be :

a_ Identified LEAKAG E

1. LEAKAGE, such as that fro m pu mp seals or valv e packing (except react or coolant pu mp (RCP) seal water injection or leakoff), that is captured and conducted to collection sy stem s or a su mp or collecting tank;

2. LEAKAG E into t he contain ment atmosphere from sources that are- both specificall)l"locate dl and known eithe r not to interfere-with the operation of leak.age detection syste ms or not to be pressure boundary LEAKAG E; or

3. Reactor Coolant Sy st em (RCS) LEAKAG E through a steam g:enerator to the Secondary Sy stem (pri mary to secondary LEAKAG E);

INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50 .55a(f) .

(continued)

V ogtle Units 1 and 2 1.1-3 Amend ment No. -t¢¢- (Unit 1)

Amend ment No. ~ (Unit 2)

Pressurizer Safety Valves 3.4.10 SURV EILLANCE REQUIRE MENTS SURVEILLANCE FREQU ENCY S R 3.4.10.1 V erify each pressurizer safety v alv e is O PE RABLE in accordance with the IRseNiee Testing, Program_ Followi ng testin g, lift settings shall be within+/- 1% _

Vogtle Units 1 and 2 3.4.10-2 Amendment No.-96--(Unit 1)

Amendment No.- 'fir (Unit 2)

RCS PIV Leakage 3.4.14 SURV EIU.ANCE REQUIREMENTS SURV EILLANCE FREQUENCY SR 3.4.14.1 - ----NOTES-----------

1. Not required to be performed in MODES 3 and 4.

2. Not required to be performed on the RCS PIV s located in the RHR flow path when in the shutdown cool ing mode of operation .

3. RCS PIV s actuated during the performance of th is Surveillance are not requ ired to be tested more than once if a repetitiv e testing loop cannot be av oided.

V erify leakage fro m each RCS PIV is equiv alent In accordance with to s;; 0.5 gpm perno minal inch of v alv e size up to the LRserviee Tes~i flg a maximum of 5 gpm at an RCS pressure Prog1a111, and

~ 2215 psig and s;; 2255 psig. 18 months Prior to entering MOD E 2 whenev er the unit has been in MOD E 5 for 7 days or more, if leakage testing has not been performed in the previ ous 9 months (except for v alv es HV-8701AIB and HV -

8702AIB)

AND (continued)

V ogtle Units 1 and 2 3.4.14-3 A mendment No: (Unit 1)

A mendment No.-+4-(Unit 2}

ECCS-Operating 3-5.2 SU RVEILLANCE REQU IREMENTS SURVEILLANCE FREQUENCY S R 3_5_2_1 V erify t he following.v alv es are in the li sted In accordance with po sition with the power lo ck out switches in the the Surveillance lockout position_ Frequency Control Program V alv e Nu mbe r Valv e Function Valv e Position HV -8835 SI Pump Cold Le g lnj_ OPEN HV-8840 RHR Pump Hot Legi !nj _ CbOS ED HV -8813 S I Pump Mini Flow lsol _ OPEN HV -8806 SI Pump Suction fro m RWST OPE N HV -8802A, B SI Pump Hot Leg lnj _ CLO SED HV-8809A, B RHR Pump Cold Leg, lnj _ OPEN SR 3.5.2_2 V erify each ECCS manual, power op erated, and In accordance with auto matic v alv e in the flow path , that is not the Surveillance locked, sealed, or otherwise secured in position, Frequency Control is in the correct position _ Program SR 3-5.2.3 V erify ECCS piping' is full of water. In accordance with the Surveillance Frequency Control Program SR 3.5.2.4 V erify each ECCS pump' s dev elope d head at the In accordance with test flow po int is greater than or equal to t he t he lnsentice Testing requ ire d dev elo ped head_ Program 1'

SR 3-5.2.5 V erify each ECCS automatic v alv e in the flow In accordance with path that is not lock ed, sealed, or othe rwise the Surveillance secured in position actuates to the correct Frequency Control position on an actual or simulated actuation Program sign al_

_/ (continued)

~RVICE TESTING PROGRAM Vogtle Units 1 and 2 3 5.2-2 Amendment No. -+58- (Unit 1}

Amendment No4i:e (Unit 2}

Containment Isolation Valves 3.6.3 SURVEIL LANCE REQUIREMENfliS (continue d)

SURVEI UANCE FREQUENCY SR 3.6.3.4 -NOlES-- -- - - -- -- -

1. Valves and! blind flanges in high radiation areas may be v erifie d by use of admi nistrativ e* means .

2. lhe fuel transfertube blind flange is only requ ire d to* be v erifiediclosed: once after refuelingi prior to entering MODE 4 fro m MODES.

V erify each contain ment isolation manual valv e Prior to ent eringi and bl ind flange that is locate d inside contain ment MODE 4 fro m and req,uiredl to be close d during accident MODE 5 if not conditions is closed, except' forcontain ment performed within the isolation valves that are open under prev ious 92 day s administrativ e controls .

SR 3.6.3.5 V erify the isolation time of each power operated In accordance and each automatic containment isolation valv e is with the l'Aserviee within limits. TestiAg Prugr=am

/1 SR 3.6.3.6 leaka~e Perform purge v alv es with resilient seals. 7 rat e _t_esting for containment / In accordance with the Surveillance

~ Frequency Control INSERVICE TESTING PROGRAM) Program SR 3.6.3.7 V erify each .automatic containment isolation valv e l'n accordance with that is not locked, sealed, or otherwise secured in the Surveillance position , actu ates to the isolation position on an Frequency Control actu al or si mulated actuation signal. Program Vogtle Units 1 and 2 3.6.3-5 Amendment No . ~ (Unit 1)

Amendment No.-+4G- (Unit 2)

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each contain ment spray manual, power In accordance with operated, and auto matic v alv e in the flow path the Surveillance that is not locked, sealed, or otherwise secured in Frequency Control position is in the correct position . Program SR 3.6.6.2 Operate each contain ment cool ing train fan unit In accordance with for:2: 15 mi nutes. the Su rv eillance Frequency Control Program SR 3.6.6.3 V erify each pair of contain ment fan coolers In accordance with cooling water flow rate is :2: 1359 gpm. the Surveillance Frequency Control Program SR 3.6.6.4 Verify each contain ment spray pump' s dev eloped In accordance with head at the flow test point is greater than or equal the IF1seFViee TestiF19

~

to the required dev eloped head. ~::i _ , ..

1' SR 3.6.6.5 V erify each aut omat ic contain ment spray v alv e in n accordance with the flow path that is not locked, sealed, or the Surve illance othe rwise secured in position actuates t o the Frequency Control correct position on an actual or si mulated Program actuation signal.

I SR 3.6.6.6 Verify each contain ment spray pu mp starts In accordance with automatically on an actual or simulated actuation the Surveillance signal. Fre quency Control Program (continued)

~ERVICE TESTING PROGRAM Vogtle Units 1 and 2 3.6.6-2 Amendment No.-1'5'tt (Unit 1)

Amendment No _...:t4Q... (Unit 2)

MSSVs 3.7.1 ACTIONS (continu ed)

CONDITl:ONI REQUI RED ACTION COMPLETION TIM E EL Re quire d Action an d B.1'. Be in MODE 3. '6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ass o ci afe d Campi eti on lime not met AND OR B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months One or more steam generators (SG) with four or morn MSSVs per SG inoperable.

SURVEILLANCE REQUIREMENJS S URVElllANCE FREQU ENCY SR 3.7.1.1 - - -- - -NOTE----- - - -

Only required to be pe rformed in MODES 1 and 2.

Veri fy each required MSSV li ft setpoint per In acco rdance with Table 3.7. 1-2 in accordance with th e lnservice th e l'nservice Testing.

. Following te sting, lift settings Pm9.ram shall be within +/- 1i%.

Vogtle Units 1 and 2 3. 7.1-2 Amend ment Ncr.96- (Unit 1)

Amend ment No.-14-(Unit 2)

MSIVs 3.7.2 ACTIONS (continued)

CONDmON REQUIRED ACTI:ON: COMPLETION TIM E D. One or m ore steam lines D.1 V erify one MSIV sy ste m 7 day s with one MSIV sy ste m closed in affected steam inoperable in MOD E 2 or line . AND 3.

Once per 7 day s thereafter.

E. One or more steam lines E.1 V erify one MSIV sy ste m 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with two MS l:V sy ste ms dosed in affected steam inoperable in MOD E 2 or line . AND 3.

- Once per 7 day s thereafter F. Required Action and f.1, Be in MOD E 3. i6 hours associated Co mpletion Ti me of Condition D or AND E not met F.2 Be in MOD E 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURV EILl!.ANCE REQUIRE MENTS SURV EILlANCE FREQUENCY SR 3.7.2 .1 -NOTE--- - --- - - - -

Only required to be performed in MOD ES 1 and 2.

V erify closure ti me of each MSl,V sy ste m is In accordance with the s 5 seconds on an actual or si mulated actuation li 1se1 vice Tes tin~

siQnal. Pm gram Vogtle Units 1 and 2 3 7.2-2 Amendment No,..-%- (Unit 1}

Amendment No:-11t- (Unit 2)

MFIVs and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS (continued)

CONDmON REQUIRED ACTION' COMPLETION TIME C. One or more MFRV or C.1 Close or isolate bypass 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months MFIV bypass v alv es valve.

inoperable.

AND C.2 Verify bypass v alv e is Once per 7 day s closed or isolated.

0. Both isolation sy ste ms D.1 l:solate affecte d feedwater 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable in one or line.

more feedwater lines.

E. Required Action and E.1 Be in MODEJ _ '6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Co mpletion Time not met SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 NOTE- -- - - - - -- - -

Only requ ired to be performed in MODE 11_

V erify the closure time of each MFIV, MFRV, and l'n accordance with associated bypass valv e is~ 5 secon ds on an the IRservice Test-iRg actual or si mulated actuation signal. Pr=ogr=am INSERVICE TESTING PROGRAM Vogtle Units 1 and 2 3.7.3-2 Amendment No.-9& (Unit 1)

Amendment No. (Unit 2)

UHS 3.7.9 SU RV EIU.ANCE REQUI REMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water lev el of NSCW basin is~ 80.25 ft In accordance with the Surveillance Frequency Control Program SR 3.7.9.2 V erify water te mperature of NSCW basin is In accordance with the

~ 90°F. Surveillance Frequency Control Program SR 3.7.9.3 Operate each required NSCW cool ing tower fan In accordance with t he for~ 15 minutes. Surveillance Frequency Control Program SR 3.7.'9.4 V erify NSCW basin transfer pump operation . In accordance with t he lnse!'l'ice Testing

~SER~~ PR2_G~ PF0~f9:ffi SR 3.7.'9.5 V erify ambient wet-bulb te mperature is with in the In accordance with the three fan/ spray cell region of Figure 3.7.9-1! when Surveillance one NSCW tower fan/ spray cell is out-of-service Frequency Control and daily high te mperature (dry-bulb) is Program forecaste d to be > 48"F.

Vogtle Units 1 and 2 3.7 9-3 Amendment No. 4+{}- (Unit 1)

Amendment No. +52-(Unit 2)

Programs and Manuals 5_5 5.5 Programs and Manuals

~6iused J 5-5.8 lflserviee Testifl §i Program

s program prov ides controls forinserv ice testing of ASME Code Class 1, 2, components _ The program shall include*the following :

a_ Te

g frequencies specified in Section XII of the ASM E Boiler a Press e Vessel Code and applicable Addenda as follows :

ASME Boi ler and Pre sure Vessel Code and appli le Required Fr ,uencies for Addenda terminology for performin inservice inservice testing activities testin ctivitie*s Weekly

east once per 7 days Monthly t least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every t least once per 184 days 6 months Every 9 months At le t once per276 days Yearly or annually At least ce per 366 days Biennially or every 2 year At least on per 731 days b_ The provisio of SR 3.0.2 are applicable to the above for performing inservice testing activities ;

c. The ovisions of SR 3_0_3 are applicable to inservice testing a *vities ; and d_ othing in the ASME Boiler and Pressure Vessel Code shall be cons

ed to supersede the requirements of any TS _

{continued)

Vogtle Units 1 and 2 5.5-6 Amendment No. 44:¢- (Unit 1)

Amendment No.-4Z>t (Unit 2)

Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, "TS lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing," and to Request an Alternative to the ASME Code Enclosure 3 FNP, HNP, and VEGP Technical Specification Clean Typed Pages

Definitions 1.1 1 .1 Definitions ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval from FEATURE(ESF)RESPONSE when the monitored parameter exceeds its ESF actuation TIME setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e ., the valves travel to their required positions, pump discharge pressures reach their required values , etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential , overlapping , or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC .

INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM program that fulfills the requirements of 10 CFR 50.55a(f) .

LEAKAGE LEAKAGE shall be:

a.. Identified LEAKAGE

1. LEAKAGE , such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff) , that is captured and conducted to collection systems or a sump or collecting tank;

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE ; or

3. Reactor Coolant System (RCS) LEAKAGE through a steam generator (SG) to the Secondary System ;

b. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE ;

(continued)

Farley Units 1 and 2 1.1-3 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Pressurizer Safety Valves 3.4 .10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE in In accordance with accordance with the INSERVICE TESTING the INSERVICE PROGRAM . Following testing , lift settings shall be TESTING within+/- 1%. PROGRAM Farley Units 1 and 2 3.4 .10-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

LTOP System 3.4 .12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4 .12.1 Verify a maximum of one charging pump is In accordance with capable of injecting into the RCS when one or more the Surveillance RCS cold legs is s 180°F. Frequency Control Program SR 3.4.12.2 Verify a maximum of two charging pumps are In accordance with capable of injecting into the RCS when all RCS cold the Surveillance legs are > 180°F. Frequency Control Program SR 3.4 .12.3 Verify each accumulator is isolated . In accordance with the Surveillance Frequency Control Program SR 3.4.12.4 Verify RHR suction isolation valves are open for each In accordance with required RHR suction relief valve. the Surveillance Frequency Control Program SR 3.4 .12.5 -----------------------------N 0 TE--------------------------------

Only required to be performed when complying with LCO 3.4.12 .b.

Verify RCS vent ::::: 2.85 square inches open . In accordance with the Surveillance Frequency Control Program SR 3.4 .12.6 Verify each required RHR suction relief valve In accordance with setpoint. the INSERVICE TESTING PROGRAM AND In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.4.12-4 Amendment No. (Unit 1)

Amendment No. (Unit 2)

ECCS- Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 ----------------------------NOTE---------------------------------

Only required to be performed for valves 8132A and 81328 when Centrifugal Charging Pump A is inoperable.

Verify the following valves are in the listed position In accordance with with power to the valve operator removed. the Surveillance Frequency Control Number Position Function Program 8884,8886 Closed Centrifugal Charging Pump to RCS Hot Leg 8132A, 8132B Open Centrifugal Charging Pump discharge isolation 8889 Closed RHR to RCS Hot Leg Injection SR 3.5.2.2 Verify each ECCS manual, power operated, and In accordance with automatic valve in the flow path , that is not locked , the Surveillance sealed , or otherwise secured in position , is in the Frequency Control correct position. Program SR 3.5.2 .3 Verify each ECCS pump's developed head at the test In accordance with flow point is greater than or equal to the required the INSERVICE developed head . TESTING PROGRAM SR 3.5.2.4 Verify each ECCS automatic valve in the flow path In accordance with that is not locked, sealed , or otherwise secured in the Surveillance position , actuates to the correct position on an actual Frequency Control or simulated actuation signal. Program Farley Units 1 and 2 3.5.2-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3 .3 ----------------------------NOTES--------------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of admin istrative means.

2. The blind flange on the fuel transfer canal flange is only required to be verified closed after each draining of the canal.

Verify each containment isolation manual valve and Prior to entering blind flange that is located inside containment and MODE 4 from not locked, sealed , or otherwise secured and MODE 5 if not required to be closed during accident conditions is performed within closed , except for containment isolation valves that the previous are open under administrative controls. 92 days SR 3.6.3.4 Verify the isolation time of each power operated In accordance with or automatic containment isolation valve in the the INSERVICE INSERVICE TESTING PROGRAM is within limits. TESTING PROGRAM SR 3.6 .3.5 Perform leakage rate testing for containment In accordance with penetrations containing containment purge valves the Surveillance with resilient seals . Frequency Control Program AND Within 92 days after opening the valve SR 3.6.3.6 Verify each automatic containment isolation valve In accordance with that is not locked , sealed or otherwise secured in the Surveillance position , actuates to the isolation position on an Frequency Control actual or simulated actuation signal. Program Farley Units 1 and 2 3.6.3-6 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Containment Spray and Cooling Systems 3.6 .6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.4 Verify each containment spray pump's developed In accordance with head at the flow test point is greater than or equal to the INSERVICE the required developed head. TESTING PROGRAM SR 3.6.6.5 Verify each automatic containment spray valve in the In accordance with flow path that is not locked, sealed , or otherwise the Surveillance secured in position , actuates to the correct position Frequency Control on an actual or simulated actuation signal. Program SR 3.6.6.6 Verify each containment spray pump starts In accordance with automatically on an actual or simulated actuation the Surveillance signal. Frequency Control Program SR 3.6.6.7 Verify each containment cooling train starts In accordance with automatically on an actual or simulated actuation the Surveillance signal. Frequency Control Program SR 3.6.6.8 Verify each spray nozzle is unobstructed . In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.6.6-3 Amendment No. (Unit 1)

Amendment No. (Unit 2)

MSSVs 3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 -------------NOTE------------

Only required in MODE 1.

Reduce the Power Range 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Neutron Flux-High reactor trip setpoint to less than or equal to the Maximum Allowable % RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR One or more steam generators with 2".: 4 MSSVs inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 ---------------------------------N 0 TE----------------------------

0 nIy required to be performed in MODES 1 and 2.

Verify each required MSSV lift setpoint per Table In accordance with 3.7.1-2 in accordance with the INSERVICE TESTING the INSERVICE PROGRAM . Following testing , lift setting shall be TESTING within +/-1 %. PROGRAM Farley Units 1 and 2 3.7.1-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

MS IVs 3.7 .2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. One or more steam lines E.1 Verify one MSIV closed in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with two MSIVs affected steam line.

inoperable in MODE 2 AND or 3.

Once per 7 days thereafter F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition D or E AND not met.

F.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7 .2.1 -------------------------------N 0 TE-------------------------------

0 nIy required to be performed in MODES 1 and 2.

Verify closure time of each MSIV is ~ 7 seconds . In accordance with the INSERVICE TESTING PROGRAM Farley Units 1 and 2 3.7 .2-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One or more MFRV C.1 Close or isolate bypass 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months bypass valves valve .

inoperable.

AND C.2 Verify bypass valve is closed Once per. 7 days or isolated.

D. Two valves in the same D.1 Isolate affected flow path . 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow path inoperable.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each Main FW Stop Valve, In accordance with MFRV, and associated bypass valve is in accordance the INSERVICE with the time requirement in the lnservice Testing TESTING Plan . PROGRAM Farley Units 1 and 2 3.7.3-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.2 -----------------------------N 0 TE---------------------------------

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after ~ 1005 psig in the steam generator.

Verify the developed head of each AFW pump at the In accordance flow test point is greater than or equal to the required with the developed head . INSERVICE TESTING PROGRAM SR 3.7.5.3 Verify each AFW automatic valve that is not locked , In accordance sealed , or otherwise secured in position , actuates to with the the correct position on an actual or simulated Surveillance actuation signal. Frequency Control Program SR 3.7.5.4 ----------------------------NOTE----------------------------------

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after~ 1005 psig in the steam generator.

Verify each AFW pump starts automatically on an In accordance actual or simulated actuation signal. with the Surveillance Frequency Control Program SR 3.7.5.5 Verify the turbine driven AFW pump steam admission In accordance valves open when air is supplied from their respective with the air accumulators. Surveillance Frequency Control Program Farley Units 1 and 2 3.7.5-3 Amendment No. (Unit 1)

Amendment No . (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Reactor Coolant Pump Flywheel Inspection Program (continued)

b. A surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the disassembled flywheel.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel Inspection Program .

5.5.8 Not used.

5.5.9 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained . In addition , the Steam Generator Program shall include the following :

a. Provisions for condition monitoring assessments. Condition monitoring (continued)

Farley Units 1 and 2 5.5-5 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Definitions 1.1 1.1 Definitions (continued)

END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that time interval RECI RC ULATION from initial signal generation by the associated turbine stop valve limit PUMP TRIP switch or from when the turbine control valve hydraulic control (EOC-RPT) oil pressure drops below the pressure switch setpoint to complete SYSTEM suppression of the electric arc between the fully open contacts of the RESPONSE TIME recirculation pump circuit breaker. The response time may be measured by means of any series of sequential , overlapping , or total steps so that the entire response time is measured .

INSERVICE The INSERVICE TESTING PROGRAM is the licensee program that fulfills TESTING the requirements of 10 CFR 50.55a(f) .

PROGRAM LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE into the drywell, such as that from pump seals or valve packing , that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE ;

b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE ;

d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall , or vessel wall.

LINEAR HEAT LINEAR HEAT GENERATION RATE (LHGR) shall be the power generation GENERATION in an arbitrary length of fuel rod , usually six inches. It is the integral of the RATE heat flux over the heat transfer area associated with the unit length .

LOGIC SYSTEM A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all FUNCTIONAL required logic components (i.e., all required relays and contacts , trip TEST units, solid state logic elements, etc.) of a logic circuit, from as close to the sensor as practicable up to, but not including , the actuated device , to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential , overlapping , or total system steps so that the entire logic system is tested .

(continued)

HATCH UNIT 1 1.1-3 Amendment No.

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.7 Verify each pump develops a flow rate <:: 41.2 gpm In accordance at a discharge pressure<:: 1232 psig . with the INSERVICE TESTING PROGRAM SR 3.1.7.8 Verify flow through one SLC subsystem from pump In accordance with into reactor pressure vessel. the Surveillance Frequency Control Program SR 3.1.7.9 Verify all heat traced piping between storage tank In accordance with and pump suction is unblocked. the Surveillance Frequency Control Program Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after pump suction piping temperature is restored within the Region A limits of Figure 3.1.7-2 SR 3.1.7.10 Verify sodium pentaborate enrichment is Prior to addition to

<:: 60 .0 atom percent B-10. SLC tank HATCH UNIT 1 3.1-20 Amendment No.

S/RVs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4 .3.1 Verify the safety function lift setpoints of the S/RVs In accordance with are as follows : the INSERVICE TESTING Number of Setpoint PROGRAM S/RVs {Qfilg)_

11 1150 +/- 34.5 Following testing , lift settings shall be within +/- 1%.

HATCH UNIT 1 3.4-6 Amendment No .

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.6 ----------------------------N 0 TE-------------------------------

0 n ly required to be performed prior to entering MODE 2 from MODE 3 or 4 , when in MODE 4

> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Verify each recirculation pump discharge valve In accordance with cycles through one complete cycle of full travel or the Surveillance is de-energized in the closed position . Frequency Control Program SR 3.5.1.7 Verify the following ECCS pumps develop the In accordance with specified flow rate against a system head the INSERVICE corresponding to the specified reactor pressure. TESTING PROGRAM SYSTEM HEAD CORRESPONDING NO. OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF cs ~ 4250 gpm 1 ~ 113 psig LPCI ~17 , 000gpm 2 ~ 20 psig SR 3.5.1.8 ----------------------------N 0 TE-------------------------------

N ot required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure ~ 1058 psig and In accordance with

920 psig , the HPCI pump can develop a flow the Surveillance rate ;;

: 4250 gpm against a system head Frequency Control corresponding to reactor pressure. Program (continued)

HATCH UNIT 1 3.5-4 Amendment No.

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for each required ECCS injection/ spray In accordance with subsystem, the piping is filled with water from the the Surveillance pump discharge valve to the injection valve. Frequency Control Program SR 3.5.2.4 ----------------------------N 0 TE------------------------------

0 ne LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS injection/spray In accordance with subsystem manual , power operated , and the Surveillance automatic valve in the flow path , that is not locked, Frequency Control sealed , or otherwise secured in position, is in the Program correct position .

SR 3.5.2.5 Verify each required ECCS pump develops the In accordance with specified flow rate against a system head the INSERVICE corresponding to the specified reactor pressure. TESTING PROGRAM SYSTEM HEAD CORRESPONDING NO. OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF cs ~ 4250 gpm 1 ~ 113 psig LPCI ~ 7700 gpm 1 ~ 20 psig SR 3.5.2 .6 ---------------------------N 0 TE--------------------------------

Ve sse I injection/spray may be excluded.

Verify each required ECCS injection/spray In accordance with subsystem actuates on an actual or simulated the Surveillance automatic initiation signal. Frequency Control Program HATCH UNIT 1 3.5-8 Amendment No.

PC IVs 3 .6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6 .1.3.2 ------------------------------N 0 TES---------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means .

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual In accordance with valve and blind flange that is located outside the Surveillance primary containment and is required to be closed Frequency Control during accident conditions is closed . Program SR 3.6 .1.3 .3 -----------------------------N 0 TES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual isolation Prior to entering valve and blind flange that is located inside MODE 2 or 3 from primary containment and is required to be closed MODE 4 if primary during accident conditions is closed . containment was de-inerted while in MODE 4 , if not performed within the previous 92 days SR 3.6 .1.3.4 Verify continuity of the traversing incore probe In accordance with (TIP) shear isolation valve explosive charge . the Surveillance Frequency Control Program SR 3.6 .1.3 .5 Verify the isolation time of each power operated In accordance with and each automatic PCIV, except for MSIVs, is the INSERVICE within limits. TESTING PROGRAM (continued)

HATCH UNIT 1 3.6-11 Amendment No.

PC IVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3 .6 Verify the isolation time of each MSIV is In accordance with

~ 3 seconds and :::; 5 seconds. the INSERVICE TESTING PROGRAM SR 3.6.1.3.7 Verify each automatic PCIV, excluding EFCVs , In accordance with actuates to the isolation position on an actual or the Surveillance simulated isolation signal. Frequency Control Program SR 3.6.1 .3.8 Verify each reactor instrumentation line EFCV (of In accordance with a representative sample) actuates to restrict flow the Surveillance to within limits. Frequency Control Program SR 3.6.1 .3.9 Remove and test the explosive squib from each In accordance with shear isolation valve of the TIP system . the Surveillance Frequency Control Program SR 3.6.1 .3.10 Verify combined MSIV leakage rate for all four In accordance with main steam lines is :::; 100 scfh when tested at the Primary

~ 28 .0 psig and < 50.8 psig . Containment Leakage Rate OR Testing Program Verify combined MSIV leakage rate for all four main steam lines is :::; 144 scfh when tested at

~ 50 .8 psig .

SR 3.6 .1.3.11 Deleted SR 3.6.1.3.12 Cycle each 18 inch excess flow isolation damper In accordance with to the fully closed and fully open position. the Surveillance Frequency Control Program SR 3.6.1.3.13 Verify the combined leakage rate for all secondary In accordance with containment bypass leakage paths is:::; 0.02 La the Primary when pressurized to ~ Pa . Containment Leakage Rate Testing Program HATCH UNIT 1 3.6-12 Amendment No.

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time not met. AND E.2 Be in MODE 4 . 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6 .1.7.1 -----------------------------N 0 TES---------------------------

1. Not required to be met for vacuum breakers that are open during Surveillances .

2. Not required to be met for vacuum breakers open when performing their intended function .

Verify each vacuum breaker is closed . In accordance with the Surveillance Frequency Control Program SR 3.6.1.7.2 Perform a functional test of each vacuum breaker. In accordance with the INSERVICE TESTING PROGRAM SR 3.6.1 .7.3 Verify the opening setpoint of each vacuum In accordance with breaker is ~ 0.5 psid. the Surveillance Frequency Control Program HATCH UNIT 1 3.6-18 Amendment No.

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.2.3.2 Verify each required RHR pump develops a flow In accordance with rate ~ 7700 gpm through the associated heat the INSERVICE exchanger wh ile operating in the suppression pool TESTING cooling mode. PROGRAM HATCH UNIT 1 3.6-26 Amendment No.

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.5 Component Cyclic or Transient Limit This program provides controls to track FSAR Section 4.2, cyclic and transient occurrences , to ensure that reactor coolant pressure boundary components are maintained within the design limits .

5.5.6 Not Used 5.5.7 Ventilation Filter Testing Program (VFTP)

The VFTP will establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52 ,

Revision 2, Sections C.5.c and C.5.d, or: 1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, 2) following painting , fire or chemical release in any ventilation zone communicating with the system , or 3) after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation .

(continued)

HATCH UNIT 1 5.0-10 Amendment No.

Definitions 1.1 1.1 Definitions (continued)

EMERGENCY The ECCS RESPONSE TIME shall be that time interval from when CORE COOLING the monitored parameter exceeds its ECCS initiation setpoint at the SYSTEM (ECCS) channel sensor until the ECCS equipment is capable of performing RESPONSE its safety function (i.e., the valves travel to their required positions ,

TIME pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential , overlapping , or total steps so that the entire response time is measured.

END OF CYCLE The EOC-RPT SYSTEM RESPONSE TIME shall be that time interval RECIRCULATION from initial signal generation by the associated turbine stop valve limit PUMP TRIP switch or from when the turbine control valve hydraulic control oil (EOC-RPT) pressure drops below the pressure switch setpoint to complete SYSTEM suppression of the electric arc between the fully open contacts of the RESPONSE TIME recirculation pump circuit breaker. The response time may be measured by means of any series of sequential , overlapping , or total steps so that the entire response time is measured .

INSERVICE The INSERVICE TESTING PROGRAM is the licensee program that TESTING fulfills the requirements of 10 CFR 50.55a(f) .

PROGRAM ISOLATION The ISOLATION SYSTEM RESPONSE TIME shall be that time interval SYSTEM from when the monitored parameter exceeds its isolation initiation RESPONSE TIME setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential , overlapping , or total steps so that the entire response time is measured .

LEAKAGE LEAKAGE shall be :

a. Identified LEAKAGE

1. LEAKAGE into the drywell, such as that from pump seals or valve packing , that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE ;

b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE ;

(continued)

HATCH UNIT 2 1.1-3 Amendment No.

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each SLC subsystem manual and power In accordance with operated valve in the flow path that is not locked , the Surveillance sealed, or otherwise secured in position is in the Frequency Control correct position, or can be aligned to the correct Program position.

SR 3.1.7.7 Verify each pump develops a flow rate ~ 41 .2 gpm In accordance at a discharge pressure~ 1232 psig . with the INSERVICE TESTING PROGRAM SR 3.1.7.8 Verify flow through one SLC subsystem from pump In accordance with into reactor pressure vessel. the Surveillance Frequency Control Program SR 3.1.7.9 Verify all heat traced piping between storage tank In accordance with and pump suction is unblocked. the Surveillance Frequency Control Program Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after pump suction piping temperature is restored within the Region A limits of Figure 3.1.7-2 SR 3.1.7.10 Verify sodium pentaborate enrichment is Prior to addition to

~ 60.0 atom percent B-10. SLC tank HATCH UNIT 2 3.1-19 Amendment No.

S/RVs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3 .1 Verify the safety function lift setpoints of the S/RVs In accordance with are as follows : the INSERVICE TESTING Number of Setpoint PROGRAM S/RVs .{Q§l9l 11 1150 +/- 34.5 Following testing , lift settings shall be within +/- 1%.

HATCH UNIT 2 3.4-6 Amendment No.

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.6 ------------------------------NOTE----------------------------

Only required to be performed prior to entering MODE 2 from MODE 3 or 4 , when in MODE 4

> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Verify each recirculation pump discharge valve In accordance with cycles through one complete cycle of full travel or the Surveillance is de-energized in the closed position . Frequency Control Program SR 3.5 .1.7 Verify the following ECCS pumps develop the In accordance with specified flow rate against a system head the INSERVICE corresponding to the specified reactor pressure. TESTING PROGRAM SYSTEM HEAD CORRESPONDING NO. OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF cs ;:: 4250 gpm 1 ;:: 113 psig LPCI ;:: 17,000 gpm 2 ;::; 20 psig SR 3.5.1.8 ---------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure~ 1058 psig and In accordance with

920 psig , the HPCI pump can develop a flow the Surveillance rate ::::: 4250 gpm against a system head Frequency Control corresponding to reactor pressure . Program (continued)

HATCH UNIT 2 3.5-4 Amendment No.

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify , for each required ECCS injection/spray In accordance with subsystem , the piping is filled with water from the the Surveillance pump discharge valve to the injection valve . Frequency Control Program SR 3.5.2.4 --------------------------NOTE--------------------------------

One LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS injection/spray In accordance with subsystem manual, power operated , and the Surveillance automatic valve in the flow path , that is not locked , Frequency Control sealed, or otherwise secured in position , is in the Program correct position .

SR 3.5.2.5 Verify each required ECCS pump develops the In accordance with specified flow rate against a system head the INSERVICE corresponding to the specified reactor pressure. TESTING PROGRAM SYSTEM HEAD CORRESPONDING NO. OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF cs ~ 4250 gpm 1 ~ 113 psig LPCI ~ 7700 gpm 1 ~ 20 psig SR 3.5.2.6 ---------------------------N0 TE-------------------------------

Ves se I injection/spray may be excluded.

Verify each required ECCS injection/spray In accordance with subsystem actuates on an actual or simulated the Surveillance automatic initiation signal. Frequency Control Program HATCH UNIT 2 3.5-9 Amendment No.

PC IVs 3 .6 .1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6 .1.3.2 ------------------------------N 0 TES---------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means .

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual In accordance with valve and blind flange that is located outside the Surveillance primary containment and is required to be closed Frequency Control during accident conditions is closed . Program SR 3.6 .1.3 .3 -----------------------------N 0 TES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls .

Verify each primary containment manual isolation Prior to entering valve and blind flange that is located inside MODE 2 or 3 from primary containment and is required to be closed MODE 4 if primary during accident conditions is closed . containment was de-inerted while in MODE 4 , if not performed within the previous 92 days SR 3.6 .1.3.4 Verify continuity of the traversing incore probe In accordance with (TIP) shear isolation valve explosive charge . the Surveillance Frequency Control Program SR 3 .6 .1.3 .5 Verify the isolation time of each power operated In accordance with and each automatic PCIV, except for MSIVs, is the INSERVICE within limits. TESTING PROGRAM (continued)

HATCH UNIT 2 3.6-11 Amendment No.

PC IVs 3.6.1 .3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6 .1.3.6 Verify the isolation time of each MSIV is In accordance with

~ 3 seconds and :s 5 seconds . the INSERVICE TESTING PROGRAM SR 3.6 .1.3.7 Verify each automatic PCIV, excluding EFCVs, In accordance with actuates to the isolation position on an actual or th e Surveillance simulated isolation signal. Frequency Control Program SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV (of In accordance with a representative sample) actuates to restrict flow the Surveillance to within limits. Frequency Control Program SR 3.6.1.3.9 Remove and test the explosive squib from each In accordance with shear isolation valve of the TIP system . the Surveillance Frequency Control Program SR 3.6.1.3.10 Verify the combined leakage rate fo r all In accordance with secondary containment bypass leakage paths is the Primary

s 0.02 La when pressurized to ~ Pa. Containment Leakage Rate Testing Program SR 3.6.1.3.11 Verify combined MSIV leakage rate for all four In accordance with main steam lines is ::::: 100 scfh when tested at ;:::: the Primary 28.8 psig and < 47.3 psig . Containment Leakage Rate OR Testing Program Verify combined MSIV leakage rate for all four main steam lines is ::::: 144 scfh when tested at ;::::

47 .3 psig .

SR 3.6.1 .3.12 Deleted SR 3.6.1.3.13 Cycle each 18 inch excess flow isolation damper In accordance with to the fully closed and fully open position . the Surveillance Frequency Control Program HATCH UNIT 2 3.6-12 Amendment No.

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.1 -----------------------------NOTES---------------------------

1. Not required to be met for vacuum breakers that are open during Surveillances .

2. Not required to be met for vacuum breakers open when performing their intended function .

Verify each vacuum breaker is closed . In accordance with the Surveillance Frequency Control Program SR 3.6.1 .7.2 Perform a functional test of each vacuum breaker. In accordance with the INSERVICE TESTING PROGRAM SR 3.6.1.7.3 Verify the opening setpoint of each vacuum In accordance with breaker is s 0.5 psid . the Surveillance Frequency Control Program HATCH UNIT 2 3.6-18 Amendment No.

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.2 .3.2 Verify each required RHR pump develops a flow In accordance with rate ;?: 7700 gpm through the associated heat the INSERVICE exchanger while operating in the suppression pool TESTING cooling mode. PROGRAM HATCH UNIT 2 3.6-26 Amendment No.

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.5 Component Cyclic or Transient Limit This program provides controls to track FSAR Section 5.2, cyclic and transient occurrences , to ensure that reactor coolant pressure boundary components are maintained within the design limits.

5.5.6 Not Used 5.5.7 Ventilation Filter Testing Program (VFTP)

The VFTP will establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52 ,

Revision 2, Sections C.5.c and C.5.d, or: 1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, 2) following painting , fire or chemical release in any ventilation zone communicating with the system , or 3) after every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation.

(continued)

HATCH UNIT 2 5.0- 10 Amendment No.

Definitions 1.1 1.1 Definitions (continued)

E - AVERAGE E shall be the average (weighted in proportion to DISINTEGRATION ENERGY the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes ,

other than iodines, with half lives> 14 minutes , making up at least 95% of the total noniodine activity in the coolant.

ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time FEATURE(ESF)RESPONSE interval from when the monitored parameter exceeds its TIME ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e .,

the valves travel to their required positions, pump discharge pressures reach their required values , etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential , overlapping ,

or total steps so that the entire response time is measured .

In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC .

INSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee program that fulfills the requirements of 10 CFR 50.55a(f) .

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE ; or

3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE) ;

(continued)

Vogtle Units 1 and 2 1.1-3 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4 .10.1 Verify each pressurizer safety valve is In accordance with OPERABLE in accordance with the INSERVICE the INSERVICE TESTING PROGRAM . Following testing , lift TESTING settings shall be within +/- 1%. PROGRAM Vogtle Units 1 and 2 3.4 .10-2 Amendment No. (Unit 1)

Amendment No . (Unit 2)

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 ----------------------------N()"f ES----------------------------

1. Not required to be performed in M()DES 3 and 4.

2. Not required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.

3. RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PIV is equivalent In accordance with to ::; 0.5 gpm per nominal inch of valve size up to the INSERVICE a maximum of 5 gpm at an RCS pressure "TESTING

?: 2215 psig and ::; 2255 psig . PR()GRAM , and 18 months Prior to entering M()DE 2 whenever the unit has been in M()DE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months (except for valves HV-8701A/B and HV-8702A/B)

AND continued Vogtle Units 1 and 2 3.4.14-3 Amendment No. (Unit 1)

Amendment No. (Unit 2)

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the listed In accordance with position with the power lockout switches in the the Surveillance lockout position . Frequency Control Program Valve Number Valve Function Valve Position HV-8835 SI Pump Cold Leg lnj. OPEN HV-8840 RHR Pump Hot Leg lnj. CLOSED HV-8813 SI Pump Mini Flow lsol. OPEN HV-8806 SI Pump Suction from RWST OPEN HV-8802A, B SI Pump Hot Leg lnj. CLOSED HV-8809A, B RHR Pump Cold Leg lnj. OPEN SR 3.5.2 .2 Verify each ECCS manual, power operated , and In accordance with automatic valve in the flow path , that is not the Surveillance locked , sealed , or otherwise secured in position , Frequency Control is in the correct position . Program SR 3.5.2.3 Verify ECCS piping is full of water. In accordance with the Surveillance Frequency Control Program SR 3.5.2.4 Verify each ECCS pump's developed head at the In accordance with test flow point is greater than or equal to the the INSERVICE required developed head . TESTING PROGRAM SR 3.5.2.5 Verify each ECCS automatic valve in the flow In accordance with path that is not locked , sealed , or otherwise the Surveillance secured in position actuates to the correct Frequency Control position on an actual or simulated actuation Program signal.

(continued)

Vogtle Units 1 and 2 3.5.2-2 Amendment No. (Unit 1)

Amendment No . (Unit 2)

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6 .3.4 ----------------------------N 0 TES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. The fuel transfer tube blind flange is only required to be verified closed once after refueling prior to entering MODE 4 from MODE 5.

Verify each containment isolation manual valve Prior to entering and blind flange that is located inside containment MODE 4 from and required to be closed during accident MODE 5 if not conditions is closed , except for containment performed within the isolation valves that are open under previous 92 days administrative controls.

SR 3 .6 .3.5 Verify the isolation time of each power operated In accordance and each automatic containment isolation valve is with the INSERVICE within limits . TESTING PROGRAM SR 3 .6.3 .6 Perform leakage rate testing for containment In accordance with purge valves with resilient seals. the Surveillance Frequency Control Program SR 3.6.3 .7 Verify each automatic containment isolation valve In accordance with that is not locked , sealed , or otherwise secured in the Surveillance position , actuates to the isolation position on an Frequency Control actual or simulated actuation signal. Program Vogtle Units 1 and 2 3.6 .3-5 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power In accordance with operated , and automatic valve in the flow path the Surveillance that is not locked , sealed , or otherwise secured in Frequency Control position is in the correct position . Program SR 3.6 .6.2 Operate each containment cooling train fan unit In accordance with for ?: 15 minutes. the Surveillance Frequency Control Program SR 3.6.6.3 Verify each pair of containment fan coolers In accordance with cooling water flow rate is ?: 1359 gpm. the Surveillance Frequency Control Program SR 3.6.6.4 Verify each containment spray pump's developed In accordance with head at the flow test point is greater than or equal the INSERVICE to the required developed head . TESTING PROGRAM SR 3.6.6.5 Verify each automatic containment spray valve in In accordance with the flow path that is not locked , sealed , or the Surveillance otherwise secured in position actuates to the Frequency Control correct position on an actual or simulated Program actuation signal.

SR 3.6 .6.6 Verify each containment spray pump starts In accordance with automatically on an actual or simulated actuation the Surveillance signal. Frequency Control Program (continued)

Vogtle Units 1 and 2 3.6.6-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

MSSVs 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

B.2 Be in MODE 4 . 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months One or more steam generators (SG) with four or more MSSVs per SG inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1 .1 ----------------------------N 0 TE------------------------------

Only requ ired to be performed in MODES 1 and 2.

Verify each required MSSV lift setpoint per In accordance with Table 3.7.1-2 in accordance with the INSERVICE the INSERVICE TESTING PROGRAM . Following testing , lift TESTING PROGRAM settings shall be within +/- 1%.

Vogtle Units 1 and 2 3.7.1-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

MS IVs 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more steam lines D.1 Verify one MSIV system 7 days with one MSIV system closed in affected steam inoperable in MODE 2 or AND

3. line.

Once per 7 days thereafter.

E. One or more steam lines E.1 Verify one MSIV system 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with two MSIV systems closed in affected steam inoperable in MODE 2 or line. AND 3.

Once per 7 days thereafter F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition D or AND E not met.

F.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 ----------------------------N 0 TE-----------------------------

0 n ly required to be performed in MODES 1 and 2.

Verify closure time of each MSIV system is In accordance with the

~ 5 seconds on an actual or simulated actuation INSERVICE TESTING signal. PROGRAM Vogtle Units 1 and 2 3.7.2-2 Amendment No. (Unit 1)

Amendment No. (Unit 2)

MFIVs and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more MFRV or C.1 Close or isolate bypass 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months MFIV bypass valves valve.

inoperable.

AND C.2 Verify bypass valve is Once per 7 days closed or isolated .

D. Both isolation systems D.1 Isolate affected feedwater 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable in one or line.

more feedwater lines.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 -----------------------------NOTE-----------------------------

Only required to be performed in MODE 1.

Verify the closure time of each MFIV, MFRV, and In accordance with associated bypass valve is ~ 5 seconds on an the INSERVICE actual or simulated actuation signal. TESTING PROGRAM Vogtle Units 1 and 2 3.7.3-2 Amendment No. ~ (Unit 1)

Amendment No. (Unit 2)

UHS 3.7.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7 .9.1 Verify water level of NSCW basin is ~ 80.25 ft. In accordance with the Surveillance Frequency Control Program SR 3.7 .9.2 Verify water temperature of NSCW basin is In accordance with the

90°F. Surveillance Frequency Control Program SR 3.7 .9.3 Operate each required NSCW cooling tower fan In accordance with the for ~ 15 minutes. Surveillance Frequency Control Program SR 3.7.9.4 Verify NSCW basin transfer pump operation . In accordance with the INSERVICE TESTING PROGRAM SR 3.7 .9.5 Verify ambient wet-bulb temperature is within the In accordance with the three fan/spray cell region of Figure 3.7.9-1 when Surveillance one NSCW tower fan/spray cell is out-of-service Frequency Control and daily high temperature (dry-bulb) is Program forecasted to be> 48°F.

Vogtle Units 1 and 2 3.7.9-3 Amendment No. (Unit 1)

Amendment No. (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Not Used.

(continued)

Vogtle Units 1 and 2 5.5-6 Amendment No. (Unit 1)

Amendment No. (Unit 2)

I Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, "TS lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing," and to Request an Alternative to the ASME Code Enclosure 4 FNP, HNP, and VEGP Technical Specification Bases Marked Up Pages (for information only)

SR Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.2 and SR 3.0.3 apply in Chapter 5 only BASES when invoked by a Chapter

================================15 Specification.

SRs SR 3.0.1 through SR 3.0.4 establish the general requirements appli~ble to all Specifications and apply at all times, unless otherwise stated .

SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to .meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO .

Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when :

a. The systems or components are known to be inoperable, although still meeting the SRs; or

b. The requirements of the Surveillance(s) are known not to be met between required Surveillance performances.

Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified . The SRs associated with a test exception are only applicable when the test exception is used as an allowable exception to the requirements of a Specification .

Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given SR. In this case, the unplanned event may be credited as fulfilling the performance of the SR. This allowance includes those SRs whose performance is normally precluded in a given MODE or other specified condition .

(continued)

Farley Units 1 and 2 B3.0-13 Revision 35 I

SR Applicability B 3.0 BASES SR 3.0.1 Surveillances, including Surveillances invoked by Required Actions, do (continued) not have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERABLE status.

Upon completion of maintenance, appropriate post maintenance testing is requ ired to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 3.0 .2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established . In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function . This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed .

SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per . .. " interval.

When a Section 5.5, "Programs and SR 3.0.2 permits a 25% extension of the interval specified in the Manuals," Frequency. This extension facilitates Surveillance scheduling and specification states considers plant operating conditions that may not be suitable for that the provisions of conducting the Surveillance (e.g ., transient conditions or other ongoing SR 3.0.2 are Surveillance or maintenance activities) .

applicable, a 25%

extension of the The 25% extension does not significantly degrade the reliability that testing interval, results from performing the Surveillance at its specified Frequency. This whether stated in the is based on the recognition that the most probable result of any particular specification or Surveillance being performed is the verification of conformance with the incorporated by SRs. The exceptions to SR 3.0.2 are those Surveillances for which the reference , is 25% extension of the interval specified in the Frequency doe'll--LIL\£.L..~~..........

permitted. These exce tions are stated in the individual S ecifications. A11 exa111ple Examples of where SR 3.0.2 does not apply are the Containment Leakage Rate Testing Program required by 10 CFR 50, Appendix J, and the inservice testing of pumps and valves in accordance with applicable American Society of Mechanical Engineers Operation and Maintenance Code , as required by 10 CFR 50.55a . These programs establish testing requirements and Frequencies in accordance with the requirements of regulations. The TS cannot, in and of themselves ,

extend a test interval specified in the regulations directly or by reference .

(continued)

Farley Units 1 and 2 B 3.0-14 Revision 35

SR Applicability B 3.0 BASES SR 3.0.2 (continued) As stated in SR 3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per ... " basis. The 25% extension applies to each performance after the initial performance. The initial performance of the Required Action , whether it is a particular Surveillance or some other remedial action , is considered a single action with a single Completion Time. One reason for not allowing the 25% extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.

The provisions of SR 3.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified .

SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a When a Section 5.5, Surveillance has not been completed within the specified Frequency. A "Programs and Manuals," delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified specification states that Frequency, whichever is greater, applies from the point in time that it is the provisions of SR 3.0.3 discovered that the Surveillance has not been performed in accordance are applicable, it permits with SR 3.0.2, and not at the time that the specified Frequency was not the flexibility to defer met.

declaring the testing requirement not met in accordance with SR 3.0.3 This delay period provides adequate time to complete Surveillances that when the testing has not have been missed. This delay period permits the completion of a been completed within the Surveillance before complying with Required Actions or other remedial testing interval (includ ing measures that might preclude completion of the Surveillance.

the allowance of SR 3.0.2 if invoked by the Section The basis for this delay period includes consideration of unit conditions, 5.5 specification).

adequate planning , availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements.

(continued)

Farley Units 1 and 2 B 3.0-15 Revision 35

LTOP System B 3.4.12 BASES SURVEILLANCE SR 3.4.12.1 . SR 3.4.12.2. and SR 3.4 .12.3 (continued)

REQUIREMENTS pump start such that a single failure or single action will not result in an injection into the RCS . This may be accomplished through the Hot Shutdown Panel Local/Remote and pump control switches being placed in the Local and Stop positions, respectively, and at least one valve in the discharge flow path being closed with the position of these components controlled administratively.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

SR 3.4.12.4 Each required RHR suction relief valve shall be demonstrated OPERABLE by verifying its RHR suction isolation valves (8701A, 8701 B, 8702A and 8702B) are open . This Surveillance is only required to be performed if the RHR suction relief valve is being used to meet this LCO.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

SR 3.4.12.5 The RCS vent of;::::: 2.85 square inches is proven OPERABLE by verifying its open condition .

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

The passive vent arrangement must only be open to be OPERABLE.

This Surveillance is required to be performed if the vent is being used to satisfy the pressure relief requirements of the LCO 3.4.12b.

SR 3.4.12.6 The RHR relief valves are verified OPERABLE by testing the relief setpoint. The setpoint verification ensures proper relief valve mechanical motion as well as verifying the setpoint. Testing is performed in accordance with the I11se1"11ice Testi119 P1091a111 which is based on the requirements of the ASME OM Code (Ref. 7)~

INSERVICE TESTING PROGRAM (continued)

Farley Units 1 and 2 B 3.4 .12-11 Revision

LTOP System B 3.4.12 BASES SURVEILLANCE SR 3.4.12.6 (continued) INSERVICE TESTING PROGRAM REQUIREMENTS The RHR relief valve setpoints are verified in accordance with the Surveillance Frequency Control Program. Per the ln~el"Oiee Te~ting I

PF09Fam , if the scheduled valve exceeds the relief setpoint by 3% or greater, the remaining valve shall also be tested . The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. 10 CFR 50, Appendix G.

2. Generic Letter 88-11 .

3. ASME , Boiler and Pressure Vessel Code, Section Ill.

4. FSAR, Chapter 5.2.2.4.

5. 10 CFR 50 , Section 50.46.

6. 10 CFR 50, Appendix K.

7. ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) .

Farley Units 1 and 2 B 3.4.12-12 Revision

RCS PIV Leakage B 3.4.14 BASES SURVEILLANCE SR 3.4.14.1 (continued)

REQUIREMENTS For the two PIVs in series, the leakage requirement applies to each valve individually and not to the combined leakage across both valves. If the PIVs are not individually leakage tested , one valve may have failed completely and not be detected if the other valve in series INSERVICE meets the leakage requirement. In this situation , the protection TESTING provided by redundant valves would be lost.

PROGRAM Testing is to be performed every 18 months, a typical refueling cycle, on all PIVs listed in the TRM . The 18 month Frequency is consistent with 10 CFR 50.55a(g) (Ref. 8) as contained in the IAscrtiec TcstiAg PFegFaA'l , is within frequency allowed by the American Society of Mechanical Engineers (ASME) OM Code (Ref. 7) , and is based on the need to perform such surveillances under the conditions that apply during an outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

In order to satisfy ALARA requirements, leakage may be measured indirectly (as from performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with leakage criteria .

In addition , testing must be performed once after the valve has been opened by flow or exercised to ensure tight reseating except for RCS PIVs located in the RHR flow path (Q1/2E11V001A and B, Q1/2E11V016A and B, Q1/2E11V021A, B, C and Q1/2E11V042A and B). PIVs disturbed in the performance of this Surveillance should also be tested unless documentation shows that an infinite testing loop cannot practically be avoided . Testing must be performed after the valve has been reseated .

The leakage limit is to be met at the RCS pressure associated with MODES 1 and 2. This permits leakage testing at high differential pressures with stable conditions not possible in the MODES with lower pressures.

Entry into MODES 3 and 4 is allowed to establish the necessary differential pressures and stable conditions to allow for performance of this Surveillance. The Note that allows this provision is complementary to the Frequency of prior to entry into MODE 2. In addition , this Surveillance is not required to be performed on the RHR System when the RHR System is aligned to the RCS in the (continued)

Farley Units 1 and 2 B 3.4.14-6 Revision

ECCS - Operating B 3.5.2 BASES SURVEILLANCE SR 3.5.2.2 (continued)

REQUIREMENTS mispositioned are in the correct position . The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.5.2.3 INSERVICE TESTING PROGRAM Periodic surveillance testing of ECCS pumps to detect gross degradation caused by impeller structural damage or other hydraulic component problems is required by the ASME OM Code. This type of testing may be accomplished by measuring the pump developed head at only one point of the pump characteristic curve. For example, if measured on recirculation flow, the centrifugal charging pumps should develop a differential pressure of ~ 2323 psid and the residual heat removal pumps should develop a differential pressure of~ 145 psid . This verifies both that the measured performance is within an acceptable tolerance of the original pump baseline performance and that the performance at the test flow is greater than or equal to the performance assumed in the plant safety analysis. Testing is performed in accordance with the ln!e1 oiee Te!ting P1 ogrerii , which encompasses the ASME OM Code. The ASME OM Code provides the activities and Frequencies necessary to satisfy the requirements.

Any change in the components being tested by this SR will require reevaluation of STI Evaluation Number 558904 in accordance with the Surveillance Frequency Control Program.

SR 3.5.2.4 and SR 3.5.2.5 These Surveillances demonstrate that each automatic ECCS valve actuates to the required position on an actual or simulated SI signal and that each ECCS pump (centrifugal charging and RHR) starts on receipt of an actual or simulated SI signal. This Surveillance is not required for valves that are locked, sealed , or otherwise secured in the required position under administrative controls. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

Farley Units 1 and 2 B 3.5.2-9 Revision

Containment Isolation Valves B 3.6.3 BASES SURVEILLANCE SR 3.6.3.3 REQUIREMENTS (continued) This SR requires verification that each containment isolation manual valve and blind flange located inside containment and not locked ,

sealed , or otherwise secured and required to be closed during accident conditions is closed . The SR helps to ensure that post accident leakage of radioactive fluids or gases outside of the containment boundary is within design limits. For containment isolation valves inside containment, the Frequency of "prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days" is appropriate since these containment isolation valves are operated under administrative controls and the probability of their misalignment is low. The SR specifies that containment isolation valves that are open under administrative controls are not required to meet the SR during the time they are open . This SR does not apply to valves that are locked, sealed , or otherwise secured in the closed position , since these were verified to be in the correct position upon locking , sealing ,

or securing .

Note 1 allows valves and blind flanges located in high radiation areas to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted during MODES 1, 2, 3, and 4, for ALARA reasons. Therefore, the probability of misalignment of these containment isolation valves , once they have been verified to be in their proper position , is small . Note 2 provides an allowance to only verify the blind flange on the fuel transfer canal flange after each draining of the canal.

SR 3.6.3.4 Verifying that the isolation time of each power operated or automatic containment isolation valve in the IST Program is within limits is required to demonstrate OPERABILITY. The isolation time test ensures the valve will isolate in a time period less than or equal to that assumed in the safety analyses. The isolation time and Frequency of this SR are in accordance with the lnserviee Testing PrograA'l .

Any change in the components being tested by this SR will require reeva luation of STI Evaluation Number 558904 in accordance with the Surveillance Frequency Control Program .

INSERVICE TESTING PROGRAM (continued)

Farley Units 1 and 2 B 3.6.3-12 Revision

Containment Spray and Cooling Systems B 3.6.6 BASES SURVEILLANCE SR 3.6.6 .2 (continued)

REQUIREMENTS Any change in the components being tested by this SR will require reevaluation of STI Evaluation Number 558904 in accordance with the Surveillance Frequency Control Program .

SR 3.6.6 .3 Verifying that the SW flow rate to each containment cooling train is

1600 gpm provides assurance that the design flow rate will be achieved (Ref. 3) . However, safety analyses show that, under post-accident conditions, a flow rate of 600 gpm to one fan unit is sufficient to meet the post-accident heat removal requirements. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

SR 3.6.6.4 Verifying each containment spray pump's developed head at the flow test point is greater than or equal to the required developed head ensures that spray pump performance has not degraded during the cycle. On recirculation flow each pump develops a discharge pressure of;:: 210 psig . On full flow testing , each pump is run and the flow directed through the containment spray system test line into the refueling canal. The flow is throttled across the pump curve via the regulating globe valve in the test line. Flow and differential pressure are normal tests of centrifugal pump performance required by the ASME Code for Operation and Maintenance of Nuclear Power Plants (Ref. 6). Since the containment spray pumps cannot be tested with flow through the spray headers, they are tested on recirculation flow and full flow to the refueling canal. Taken together, these tests confirm the pump design curve and are indicative of overall performance. Such inservice tests confirm component OPERABILITY, trend performance, and detect incipient failures by abnormal performance. The Frequency of the SR is in accordance with the lnservioe Tesling Progmn:i .

INSERVICE ~

TESTING :..---;:;:ny change in the components being tested by this SR will require PROGRAM reevaluation of STI Evaluation Number 558904 in accordance with the Surveillance Frequency Control Program .

(continued)

Farley Units 1 and 2 B 3.6.6-9 Revision

MSSVs B 3.7.1 BASES APPLICABLE MSSVs on the same steam generator it is necessary to prevent this SAFETY ANALYSES power increase by lowering the Power Range Neutron Flux-High (continued) setpoint to an appropriate value. When the Moderator Temperature Coefficient (MTC) is positive, the reactor power may increase above the initial value during an RCS heatup event (e.g., turbine trip) . Thus, for any number of inoperable MSSVs it is necessary to reduce the trip setpoint if a positive MTC may exist at partial power conditions, unless it is demonstrated by analysis that a specified reactor power reduction alone is sufficient to prevent overpressurization of the steam system .

The maximum allowable power levels specified in Table 3.7.1-1 are overly conservative at middle and end-of-life conditions, when the MTC is not positive. Therefore, a specific analysis which credits a middle-of-life MTC was performed to relax the power reduction associated with one inoperable MSSV per steam generator. In addition , for the above case, no reduction in the Power Range Neutron Flux-High trip setpoint is required . The middle-of-life analysis assumes a -1 O pcm/degree F MTC and demonstrates that the maximum allowable power level associated with one inoperable MSSV per steam generator can be relaxed to 87% RTP when core average burnup is~ 14,000 MWD/MTU. The MTC value at 14,000 MWD/MTU is verified to be more negative than -10 pcm/degree F for each reload cycle.

The MSSVs are assumed to have two active and one passive failure modes. The active failure modes are spurious opening , and failure to reclose once opened . The passive failure mode is failure to open upon demand .

The MSSVs satisfy Criterion 3 of 10 CFR 50 .36(c)(2)(ii).

LCO The accident analysis requires that five MSSVs per steam generator be OPERABLE to provide overpressure protection for design basis transients occurring at 102% RTP . The LCO requires that five MSSVs per steam generator be OPERABLE in compliance with Reference 2, and the OBA analysis.

The OPERABILITY of the MSSVs is defined as the ability to open upon demand within the setpoint tolerances, to relieve steam generator overpressure, and reseat when pressure has been reduced . The OPERABILITY of the MSSVs is determined by periodic surveillance testing in accordance with the lnserviee Testing PFegFaA'I .

INSERVICE TESTING PROGRAM~ (continued)

Farley Units 1 and 2 B 3.7.1-3 Revision

MSSVs B 3.7.1 BASES ACTIONS B.1 and B.2 (continued) reasonable time to correct the MSSV inoperability, the time required to perform the power reduction , operating experience in resetting all channels of a protective function , and on the low probability of the occurrence of a transient that could result in steam generator overpressure during this period .

The maximum THERMAL POWER corresponding to the heat removal capacity of the remaining OPERABLE MSSVs is determined via a conservative heat balance calculation as described in the attachment to Reference 6, with an appropriate allowance for Nuclear Instrumentation System trip channel uncertainties.

Required Action B.2 is modified by a Note, indicating that the Power Range Neutron Flux-High reactor trip setpoint reduction is only required in MODE 1. In MODES 2 and 3, the reactor protection system trips specified in LCO 3.3.1 , "Reactor Trip System Instrumentation," provide sufficient protection .

The allowed Completion Times are reasonable based on operating experience to accomplish the Required Actions in an orderly manner without challenging unit systems.

C.1 and C.2 If the Required Actions are not completed within the associated Completion Time, or if one or more steam generators have ~ 4 inoperable MSSVs, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

SURVEILLANCE SR 3.7.1.1 REQUIREMENTS This SR verifies the OPERABILITY of the MSSVs by the verification of each MSSV lift setpoint in accordance with the lnservioe Testing PFogFal"l'I . ~-.-----~-- INSERVICE TESTING PROGRAM The plant IF1seRtiee Testiflg PFOgFal"l'I incorporates the requirements of the applicable edition of the ASME OM Code (Ref. 4) as modified (continued)

Farley Units 1 and 2 B 3.7.1-6 Revision

MS IVs B 3.7.2 BASES SURVEILLANCE SR 3.7.2.1 (continued) INSERVICE TESTING PROGRAM REQUIREMENTS accident and containment analyses. This Surveillance is normally performed while returning the unit to operation following a refueling outage.

The Frequency is in accordance with the lnservice Testing Program ,

which encompasses the ASME OM Code (Ref.5) . Operating experience has shown that these components usually pass the Surveillance when performed in accordance with the lnservice Testing Program . Therefore, the Frequency is acceptable from a reliability standpoint.

This SR is modified by a Note that allows entry into and operation in MODE 3 prior to performing the SR. If desired , this allows a delay of testing until MODE 3, to establish conditions consistent with those under which the acceptance criterion was generated . This surveillance may be performed in lower modes but must be performed prior to entry into MODE 2.

REFERENCES 1. FSAR, Section 10.3.

2. FSAR, Section 6.2.

3. FSAR, Section 15.4.2.

4 . 10 CFR 100.11 .

5. ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) .

Farley Units 1 and 2 B 3.7.2-7 Revision

Main FW Stop Valves and MFRVs and Associated Bypass Valves B 3.7.3 BASES ACTIONS E.1 and E.2 (continued) experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

SURVEILLANCE SR 3.7.3.1 REQUIREMENTS This SR verifies that the closure time of each Main FW Stop Valve and MFRV and its associated bypass valve is in accordance with the requirements of the IAseFViee TestiA§ PlaA . he Main FW Stop Valve and MFRV closure times are assumed in the accident an containment analyses. This Surveillance is normally performed during return of the unit to operation following a refueling outage.

These valves should not be tested at power since even a part stroke exercise increases the risk of a valve closure with the unit generating power. This is consistent with the ASME OM Code (Ref. 2).

The Frequency for this SR is in accordance with the IRservise TestiR~

P1ogra111. Operating experience has shown that these components usually pass the Surveillance when performed in accordance with the IAserviee TestiA§ Pre§FBffi.

~ INSERVICE TESTING PROGRAM REFERENCES 1. FSAR, Section 10.4.7.

2. ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) ..

Farley Units 1 and 2 B 3.7.3-6 Revision

Containment Penetrations B 3.9.3 BASES INSERVICE TESTING PROGRAM SURVEILLANCE SR 3.9.3.2 (continued) \

REQUIREMENTS isolation time of each valve is in accordance with the IRserviee TestiFl§ Pro§FSffi requirements . These Surveillances performed during MODE 6 will ensure that the valves are capable of closing after a postulated fuel handling accident to limit a release of fission product radioactivity from the containment.

SR 3.9.3.3 The equipment hatch is provided with a set of hardware, tools, and equipment for moving the hatch from its storage location and installing it in the opening. The required set of hardware, tools, and equipment shall be inspected to ensure that they can perform the required functions.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

The SR is modified by a Note which only requires that the surveillance be met for an open equipment hatch. If the equipment hatch is installed in its opening , the availability of the means to install the hatch is not required .

REFERENCES 1. GPU Nuclear Safety Evaluation SE-0002000-001 , Rev. 0, May 20, 1988.

2. FSAR, Section 15.4.5.

3. NUREG-0800, Section 15.7.4 , Rev. 1, July 1981 .

4. Regulatory Guide 1.195, "Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors," May 2003.

Farley Units 1 and 2 B 3.9.3-6 Revision

SR Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES SRs SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.

SR 3.0.2 and SR 3.0.3 apply in Chapter 5 only when

~ invoked by a Chapter 5 Specification .

SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO.

Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in this Specification ,

however, is to be construed as implying that systems or components are OPERABLE when :

a. The systems or components are known to be inoperable, although still meeting the SRs; or

b. The requirements of the Surveillance(s) are known to be not met between required Surveillance performances.

Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified . The SRs associated with a Special Operations LCO are only applicable when the Special Operations LCO is used as an allowable exception to the requirements of a Specification.

Surveillances, including Surveillances invoked by Required Actions, do not have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERABLE status.

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 3.0.2. Post maintenance (continued)

HATCH UNIT 1 B 3.0-12 REVISION 52

SR Applicability B 3.0 BASES SR 3.0.1 testing may not be possible in the current MODE or other specified (continued) conditions in the Applicability due to the necessary unit parameters not having been established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function . This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed .

Some examples of this process are:

a. Control Rod Drive maintenance during refueling that requires scram testing at > 800 psi. However, if other appropriate testing is satisfactorily completed and the scram time testing of SR 3.1.4.3 is satisfied , the control rod can be considered OPERABLE . This allows startup to proceed to reach 800 psi to perform other necessary testing .

b. High pressure coolant injection (HPCI) maintenance during shutdown that requires system functional tests at a specified pressure. Provided other appropriate testing is satisfactorily completed , startup can proceed with HPCI considered OPERABLE . This allows operation to reach the specified pressure to complete the necessary post maintenance testing .

SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per ... " interval.

SR 3.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g ., transient conditions or other ongoing Surveillance or maintenance activities) .

When a Section 5.5, .---------7-"'

"Programs and The 25% extension does not significantly degrade the reliability that Manuals,"

results from performing the Surveillance at its specified Frequency.

specification states This is based on the recognition that the most probable result of any that the provisions of particular Surveillance being performed is the verification of SR 3.0.2 are conformance with the SRs. The exceptions to SR 3.0.2 are those applicable, a 25% Surveillances for which the 25% extension of the interval specified in extension of the the Frequency does not apply. These exceptions are stated in the testing interval , individual Specifications. The requirements of regulations take whether stated in the specification or incorporated by (continued) reference , is permitted . B 3.0-13 REVISION 52

SR Applicability B 3.0 BASES SR 3.0.2 precedence over the TS . Therefo1 e, vol 1e11 a test i11te1 val is specified

~~~~~(-co_n_t_in_u~ed) ~

in the regulations , the test interval oannot be extended by the TS , and the SR inoludes a ~Joto in the Frequency stating , "SR 3.0.2 is not Examples of where SR 3.0.2 does not apply are I/ applioable." An example of an exception wl9en tl9e test inteFVal is specified in ti 1e regulatio11s is ti 1e Note i11 ti 1e Pli111a1 y Co11tail 1111er 1t in the Primary Lealcage Rete Testing Progra111 , "SR 3.0.2 is riot applicable." Tl1is Conta inment Leakage exception is provided eeeause tl9e pregraffi already includes Rate Testing Program exte11sior 1of test intervals. 1 required by 10 CFR 50 ,

Appendix J, and the As stated in SR 3.0.2, the 25% extension also does not apply to the inservice testing of pumps initial portion of a periodic Completion Time that requires performance and valves in accordance with applicable American on a "once per ... " basis. The 25% extension applies to each Society of Mechanical performance after the initial performance. The initial performance of Engineers Operation and the Required Action , whether it is a particular Surveillance or some Maintenance other remedial action , is considered a single action with a single Code , as requi red by 1O Completion Time. One reason for not allowing the 25% extension to CFR 50 .55a . These this Completion Time is that such an action usually verifies that no prog rams establish loss of function has occurred by checking the status of redundant or testing requirements and diverse components or accomplishes the function of the inoperable Frequencies in equipment in an alternative manner.

accordance with the requi rements of regulations. The TS The provisions of SR 3.0.2 are not intended to be used repeatedly ,

cannot, in and of merely as an operational convenience to extend Surveillance intervals themselves , extend a test (other than those consistent with refueling intervals) or periodic interval specified in the Completion Time intervals beyond those specified .

regulations directly or by reference .

SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been When a Section 5.5, performed in accordance with SR 3.0.2, and not at the time that the "Programs and Manuals,"

specified Frequency was not met.

specification states that the provisions of SR 3.0 .3 are applicable, it permits This delay period provides adequate time to complete Surveillances the flexibility to defer that have been missed . This delay period permits the completion of a declaring the testing Surveillance before complying with Required Actions or other remedial requirement not met in measures that might preclude completion of the Surveillance.

accordance with SR 3.0.3 when the testing has not The basis for this delay period includes consideration of unit been completed within the conditions, adequate planning , availability of personnel , the time testing interval (includ ing required to perform the Surveillance, the safety significance of the the allowance of SR 3.0 .2 if invoked by the Section delay in completing the required Surveillance, and the recogn ition that 5.5 specification) .

(continued)

HATCH UNIT 1 B 3.0-14 REVISION 52

SLC Sy stem B 3.1-7 BAS ES SURV EILLANCE SR 3.1.7-5 REQUIREMENTS (continued) This Surveillance* requires an examination of the sodiu m pentaborate soluti on by using che mical analy sis to ensure that the proper concentration of boron exists in the storage tank (within Region A limits of figures 3.1i-7-1i an d 3.1. 7-2). SR 3.1.7.5 must be performed

.any time sodium pentaborate or water is added to the storage tan k solution to determine that the* boron solution concentration is within the sp ecified limits_ SR 3.1-7.5 must also be performed any time the temperature is restored to within the Region A limits of Figure 3.1:.7-2, to ensure that no significant boron precipfation occurred. The Surv eillance frequen cy is controlled under the Surveillance Frequen cy Control Program_

SR 3.1.7.7 Demonstrat ing that each SlC Sy ste m pump dev elops a flow rate ~ 41.2 gpm at a discharge pressure ~ 1232 psig ensures that pump performance has not degraded during the fuel cyole . This mi nimum pump flow rate require ment ensures that, when co mbined with the sodiu m pentaborate solution concentration require ments, the rate of neg:ativ e reactivity insertion fro m t he SLC Syste m wi ll adequately co mpensat e forthe positive reactivity effects encountered during power reducti on , cooloown of the moderator, and xenon decay_

Additionally, the mi nimum pump flow rate requ ire ment ensures that a dequate buffering agent will reach the suppression pool to maintain pH at or abov e 7.0 post-ILOCA_ This test confirm s one point on the pump design cu rv e and is indicativ e of ov erall performance . Such in service inspections confi rm co mponent OPE RABILITY, trend performance , an d detect incipient fai lures by indicating abno rmal performance*. The frequency of this Surveillance is in accordance with the l'n serv iee Testing PfO grsm.

INSERVICE TESTING These Su rv eillances ensure that there is a functioning flow pat h fro m PROGRAM the sodium pentaborate solution storage tan k to the RPV , including, the firing of an explosive v alve. The replacement charge for the explosiv e v alv e shall- be from the same manufactured bat ch as the one fired or fro m another batch that has been certified by having one o.fthat batch successfully fired_ The Surveillance Frequency is controlled underthe Surveillance Frequency Control Prag.ram_ The Surveillance may be performed in separate steps to prevent inj ecting boron into the RPV . An acceptable method for v erifying flow fro m the pump to th e RPV is t o pump demineralized water fro m a te*st tank (continued)

HATCH UNIT 1 B 3_1-40 REV ISION

S/RV s B 3.4.3 BAS ES (continued)

ACTIONS A.1' an d A.2 With 1 SRN inoperable, no action is required, because an analy sis de monstrated that the* re maining 10 SRNs are capable of prov iding the necessary ov erpressure protection. (See Ref. 5.)

With two or more S/RV s inoperable, a transient may result in the*

v iolation of t he ASME Code li mit on reactor pressure. The plant must be brnughH o*a MOOE in which the LCO does not apply. To achiev e t his status, the plant must be brought to M.OD E 3 wit hin 112 hours0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months an d

t o MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Ti mes are reasonable , based on operating experience , t o reach required plant conditions from full power conditions in an orderly manner and without challenging plant sy ste ms.

SURVEILLANCE SR 3.4.3.1 REQUIREMENTS This Surveillance requires that the S/RV s will open at the pressures assumed in the safety analysis of Reference 1. The de monstration of the S/RV safety lift setting,s must be performed during shutdONn , since this is a bench test, to be done in accordance with the lfl3eFtiee TestiAQi PFOgFam. The lift setting pres sure shall correspond to ambient cond'itions ofthe v alv es at nominal operating te mperatures and INSERVICE pressures . The S/RV setpoint is +/- 3% for OPERABILITY; howev er, TESTING PROGRAM ____ ,

the valv es are reset to +/- 1% during the Surveillance* to allow for drift.

The Frequency of this SR is in accordance with the l'nserviee Testing Program.

RE FERENCES 1. FSAR, Appendix M.

2. FSAR, Section 14.3.

3. INRC No.93-102, " Final Policy Statement on Technical Specification rmprov ement s," July 23, 19,93 _

4L NEDC-J2041P, "Safety Rev iew for Edwin I. Hatch Nuclear Power Plant Units 1 and 2 Updated Safety/Relie*f Valv e Performance* Requirements ," April 1996.

HATCH ur~IT 1 B 3.4-12 REVISION ._

ECCS - Operating 8 3.5.1 BAS ES SURVEI LLANCE SR 3.5.1'.6 (continued)

REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. How ev er, this SR is modified by a Note that states the Surveillance is only required to be performed priorto entering MOD E 2 fro m MODE 3 or4, when in MOD E 4> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

V erification during orfollowingMOD E 4> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and priorto enterin9 MODE 2 f rom MODE 3 or4 is an exception to the norm al

g,eneric valv e cyclin9 Frequency of 92 days , but is considered acceptable due to the de monstrate d reliability ofthese v alves. The 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is int ended to indicate an outage of sufficient duration to allow for scheduling: and proper INSERVICE performance of the Surveillance . If the valv e is inoperable and in the TESTING open po sition , the associated LPCI subsystem mu st be declared PROGRAM inoperable .

SR 3.5.1.7. SR 3.5.1.8. and SR 3.5.1.9 The performance require ments of the low pressure ECCS pu mps are determined through application of the 10 CfR 50, Appendix K criteria (Ref. 7}. This periodic Surveillance is performed (in accordance with the ASM E OM Code* require ments for the ECCS pumps) to v erify that the ECCS pu mps will dev elop the flow rates required by the respectiv e analy ses. The low pressure ECCS pu mp flow rates ensure that adequat e core cooling is provided to satisfy the acceptance criteria of Reference '9. The pump flow rates are v erified against a sy stem head equiv alent to the RPV pressure expected durin9 a L:OCA. The total system pump out.let. pres sure is adequ ate to ov ercom e the elev ation head pressure betw een the pu mp suction and the v esse'l discharg.e, the pi pin gr friction losses , and RPV pressure present during a lOCA. These v alues may be established during preoperational testing~

The flow tests fort.he HPCI Sy ste m are performed at two different pressure ranges such that sy stem capability to provi de* rated fl ow is tested at both the hi.gher and low er operatin9 ran9es o f the syste m.

The pu mp flO\N rate s are v erified against a sy stem head corre*spondngto the* RPV pressure. The total' sy stem pump out.let pressure is adequate to overcome the elev ation head pre ssure between the pu mp suction and the v essel discharge., the piping!

fricti on losses , and RPV pressure . Addlionally , ade quate steam fl ow must be passing through the main turbine or turbine by pass valves to continue*to control reactor pre ssure when the HPGI Sy stem div erts steam flow. The reactor ste am pre ssure must be~ 920 psigto perform SR 3.5. 1.8 and~ 150 psig to perform SR 3.5.1!.9. Adequate (continued)

HATCH UNIT 1 B 3.5-10 REVISION _

ECCS - Operating B 3.5. 1 BASES StJRVEILLANCE SR 35. 1.7. SR 3.5. 1.8. and SIR 3.5. 1.9 (continued)

REQUIREMENTS steam flow for SR 3-5. 1.8 is represented by at least two turbine bypass valves open , or ~ 200 MWE fro m the main turbine generator; and for SR 3.5. 11_9 adequate steam flow is represented by at least 1.25 turbine by pass valv es open, or total steam flow ~ 1E6 lb/hour.

Therefore , sufficient ti me is allowed after adequate pressure and flow are achieved! to perform these tests. Reacto r startup is allowed prior to performing.the low pressure Surveillance test because the reactor pressure is low and the ti me allowed to satisfactorily perform the Surveillance test is short The reactor pressure is allowed to be increased to no rmal operating pressure since it is assumed that the low pressure test has been satisfactorily co mpleted an d there is no indication or reason to believe that IHPCI is inoperable _ Therefore, SR 3-5. 1.8 and SR 3.5.1.9 are modi fied by Not es that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the reactor steam pressure and flow are adequate to* perfo rm the test The 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowed is sufficient to achieve stable conditions for testing and provides a reasonable ti me to co mplete i.he SR The Frequency for SR 3.5. 1i_7 is cons istent with the IRservice TesliR g Progl'3m pump testing require ments _ The Surveillance Frequency is controlled under the Surveillance Frequen cy Control Program_

INSERVICE TESTING SR 3.5.1.10 PROGRAM The ECCS subsy stems are required to actuate automatically to perform their design functi ons. This Surveillance v erifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of HPCI, GS, and LPCI will cause the syste ms or subsystems to operate as designed, including actuati on of the sy stem throughout its emergency operating sequence, automatic pump startup and actuation of all automatic valv es to their required posit ions _ Th is SR also ensures that the HPCI Sy stem will automatically restart on an RPV low water lev el (Lev el 2) signal receiv ed subsequent to an RPV high water lev el (Lev el 8) trip and that the suction is automatically transferred fro m the CST to the suppre ssion pool. The LOGIC SY STE M FUNCTIONAL TEST performed in LCO 3.3.5. 1 overlap s this Surveillance to provi de co mplete testing of the assu med safety function _

(continued}

HATCH UNIT 1 B 35-11 REVISION _

PCIVs 8 3.6.1.3 BASES SURV EILLANCE SR 3.6.1.3.5 (continued)

REQU IREMENTS closure isolation time* is demonstrated by SR 3.6.1.3.6. The isolation time test ensures that each v alv e wi ll isolate in a ti me period less than or equal to that listed in the FSAR and that no degradation affecting v alv e closure since the performance of the last Surveillance has occurred. (EFCVs are not required to be tested because they have no specified time limit). The Frequency of this S R is in accordance with the require ments of the IAservice Testifl§ Pro§Jam.

SR 3.6.1-3.6 V erifyin9that the isolation ti me of each MSIV is within the specified limits is require d to demonstrate O PERABILITY. The isolation time test ensures that the MSIV will isolate in a ti me period that does not exceed the times assumed in the OBA analyses . This ensures that the calculated radiological consequences ofthese ev ents re main within 1~ 0 CFR 50.67 limits. The Frequency of this SR is in accordance with the requ ire ments of the 1Rsel"l1iee TestiRg Program.

INSERVICE SR 3.6.1.3.7 TESTING PROGRAM Automatic PClV s dose on a primary containment isolation signal to prevent leakag.e of radioactiv e material fro m primary contain ment following a OBA. This SR ensures that each automatic PCIV wi ll actuate to its isolation position on a primary containment isolation signal. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.1.6 ov erlaps this SR to provide co mplete testing of the safety function .

The Surveillance frequency is controlled under the ~urveillance Frequency Control Program.

SR 3.6.1.3.8 This S R requires a demonstration that eaoh reactor instrumentation line excess flow check valv e (EFCV) (of a repre sentativ e sample) is OPERABLE by v erifyi ngi that the v alv e reduces flow to within limits on an actual or simulated instru ment line break condition. (The representativ e sample consists of an approxi mately equal number of EfCVs , such that each EFCV is test ed. In addition , the EFCVs (continued)

HATCH UNIT 1 B 3 . 6~24 REVISION _

Reactor Building-to-Suppression ChamberVacuum Breakers B 3.6.1.7 BAS ES SURVEILLANCE SR 3.6.1. 7.1 (continued~

REQUIREMENTS Two Notes are added to this SR The first Note allows reactor buildingi-to-suppression chamber vacuu m breakers opened in conj unction with the performance of a Surveillance to not be considered as fail ing this SR. These periods of opening v acuum breakers are controlled by plant procedures and do not represent inoperable vacuum breakers . The second Note is included to cl arify that v acuu m breakers, which are open due to an actual differential pressure , are not considered as failing this SR.

SR 3 .6.1.7.2 Each v acuu m breaker must be cycled to ensure t hat it opens properly to perform its des ign function and returns to its fully closed pos ition.

This ensures that the safety analy sis assu mptions are valid. The 92 day Frequency of th is SR is in accordance with the require ments of the IRserviee TesliRg, Prngf8:ffi.

INSERVICE TESTING Demon stration of v acuu m breaker opening setpoint is necessary to PROGRAM ensure that the safety analy sis assu mption regard ing v acuu m bre aker full open differential pressure of~ Oi.5 psid is v alid. The Surveillance Frequency is controlled under the Surv eillance Frequency Control Program.

(continued)

HATCH UNIT 1 B 3.6-39 REVISION

RHR Suppression Pool Cooling B 3.6.2.3 BASES SURV51LLANCE SR 3.6.2.3.2 REQUIREMENTS (continued) Verifyingthat each required RHR pump de el ops a flow rate

~ 7700 gpmwhile operating,in the suppression pool cooling mode with flow through the associated heat exchanger ensures that pump performance has not degraded during the cycle . Flow is a normal test of centrifugal pump performance required by ASM E OM Code*(Ref. 2). This test confirms ,one point ,on the*pump design curve , andthe results are*indicative *Of overall performance. Such INSERVICE ins ervi ce*tests confirm oo mp on ent OPERABILITY and detect in ci pie nt TESTING failures by indicating abnormal performance. The Frequencyofthis PROGRAM SR is in accordance with the lnservice Testin§ Prn§raffi.

REFERENCES 1. FSAR, Sections 5.2and14.4.3.

2. ASM E Code for Operation and Maintenance of Nuclear Power Plants.

3. NRC No.93-102 , "1Final Policy Statement on Technical Specification Improvements ," July 23, 199'3 .

HATCHUNIT1 B 3.6-58 REVISION _

SR Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES SRs SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated .

SR 3.0.2 and SR 3.0.3 apply in Chapter 5 only when

- - - - - - - - - - - - ---i invoked by a Chapter 5 Specification .

SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO .

Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in this Specification ,

however, is to be construed as implying that systems or components are OPERABLE when :

a. The systems or components are known to be inoperable, although still meeting the SRs; or

b. The requirements of the Surveillance(s) are known to be not met between required Surveillance performances.

Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified . The SRs associated with a Special Operations LCO are only applicable when the Special Operations LCO is used as an allowable exception to the requirements of a Specification.

Surveillances , including Surveillances invoked by Required Actions, do not have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERABLE status.

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 3.0.2. Post maintenance (continued)

HATCH UNIT 2 B 3.0-12 REVISION 58

SR Applicability B 3 .0 BASES SR 3.0.1 testing may not be possible in the current MODE or other specified (continued) conditions in the Applicability due to the necessary unit parameters not having been established . In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function . This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed .

Some examples of this process are:

a. Control Rod Drive maintenance during refueling that requires scram testing at > 800 psi. However, if other appropriate testing is satisfactorily completed and the scram time testing of SR 3.1.4.3 is satisfied , the control rod can be considered OPERABLE . This allows startup to proceed to reach 800 psi to perform other necessary testing .

b. High pressure coolant injection (HPCI) maintenance during shutdown that requires system functional tests at a specified pressure. Provided other appropriate testing is satisfactorily completed , startup can proceed with HPCI considered OPERABLE . This allows operation to reach the specified pressure to complete the necessary post maintenance testing.

SR 3.0.2 SR 3 .0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per .. ." interval.

SR 3.0 .2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates Surveillance scheduling and When a Section 5.5, considers plant operating conditions that may not be suitable for "Programs and conducting the Surveillance (e.g ., transient conditions or other Manuals," ongoing Surveillance or maintenance activities) .

specification states that the provisions of The 25% extension does not significantly degrade the reliability that SR 3 .0.2 are results from performing the Surveillance at its specified Frequency.

applicable, a 25% This is based on the recognition that the most probable result of any extension of the particular Surveillance being performed is the verification of testing interval , conformance with the SRs. The exceptions to SR 3 .0 .2 are those Surveillances for which the 25% extension of the interval specified in whether stated in the the Frequency does not apply. These exceptions are stated in the specification or individual Specifications. The requirements of regulations take incorporated by reference , is permitted . continued HATCH UNIT 2 B 3.0-13 REVISION 58

SR Applicability B 3.0 BASES SR 3.0.2 precedence over the TS. Tl 1erefo1 e , vvl 1e11 a test i11te1 val is specified (continued) ~ in the regulations , the test interval oannot be extended by the TS , and the SR inoludes a fl>Jote in the Frequency stating , "SR 3.0.2 is r1ot Examples of where SR _/ applioable. " An example of an mmeption when the test ir1teF11al is 3.0.2 does not apply are specified in ti 1e regulatio11s is ti 1e t<.lote ii r ti re Pli111a1 y Co11tai11111e11t in the Primary Lealcage Rate Testir1g Prograni , "SR 3.0.2 is 11ot applicable." Tl1is Containment Leakage exception is provided because the prograffi already includes Rate Testing Program exte11sio11 of test i11tervals.1 required by 10 CFR 50, Appendix J, and the As stated in SR 3.0.2 , the 25% extension also does not apply to the inservice testing of pumps initial portion of a periodic Completion Time that requires performance and valves in accordance with applicable American on a "once per ... " basis. The 25% extension applies to each Society of Mechanical performance after the initial performance. The initial performance of Engineers Operation and the Required Action , whether it is a particular Surveillance or some Maintenance other remedial action , is considered a single action with a single Code, as required by 10 Completion Time. One reason for not allowing the 25% extension to CFR 50.55a. These this Completion Time is that such an action usually verifies that no programs establish loss of function has occurred by checking the status of redundant or testing requirements and diverse components or accomplishes the function of the inoperable Frequencies in equipment in an alternative manner.

accordance with the requirements of regulations. The TS The provisions of SR 3.0.2 are not intended to be used repeatedly ,

cannot, in and of merely as an operational convenience to extend Surveillance intervals themselves , extend a test (other than those consistent with refueling intervals) or periodic interval specified in the Completion Time intervals beyond those specified.

regulations directly or by reference .

SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been When a Section 5.5, performed in accordance with SR 3.0 .2, and not at the time that the "Programs and Manuals,"

specified Frequency was not met.

specification states that the provisions of SR 3.0.3 are applicable, it permits This delay period provides adequate time to complete Surveillances the flexibility to defer that have been missed . This delay period permits the completion of a declaring the testing Surveillance before complying with Required Actions or other remedial requirement not met in measures that might preclude completion of the Surveillance.

accordance with SR 3.0.3 when the testing has not The basis for this delay period includes consideration of unit been completed within the conditions, adequate planning , availability of personnel , the time testing interval (including required to perform the Surveillance, the safety significance of the the allowance of SR 3.0.2 if invoked by the Section delay in completing the required Surveillance, and the recognition that 5.5 specification).

(continued)

HATCH UNIT 2 B 3 .0-14 REVISION 58

SLC System B 3. 1.7 BASES SURVEI LLANCE SR 3.1. 7.5 (continued)

REQUIREMENTS concentration of boron exists in the storage tan k (within Region A limits of Figures 3.1.7-1, and 3.1.7-2). SR 3.1.7.5 must be performed anyti me sodium pentaborate or water is added to the storage tan k solution to determine that the boron solution concentration is wit hin the specified limits. SR 3.1,. 7.5 must also be performed any ti me the te mperature is restored to within the Region A limits of figure 3.1.7-2, to ensure that no significant boron precipitati on occurred . The Surveil lance Frequency is controlled under the Su rv eillance Frequency Control Program.

SR 3.1.7.7 Demonstrating that each SLC Sy stem pump dev elo ps a fl ow rate~ 41 .2 gpm at a discharge pressure~ 1232 psig ensures that pump performance has not degraded during;the fuel cycle . This mini mum pu mp flow rate require ment ensures that, when co mbined with the sodium pentaborate solution concentration require ments , the rate of negativ e reactiv ity insertion from the SILC Sy stem wil l adequately co mpensate for the positive reactiv ity effects encountered during power reduction , cool down of the moderator, and xenon decay.

Additionally, the minimum pump flow rate re quirement ensures that adequate buffering agent will reach the suppress ion pool to maintain pH at or above 7.0 post-LOCA. This test confirms one point on the pump design curve and is indicativ e of ov erall performance . Such in service in spections confi rm co mponent OPERABILITY, trend performance, and detect incipient failures by indicating abno rmal performance. The Frequency of th is Su rveillance is in accordance with the IRseFViee TestiRQ ProgffHft.

INSERVICE T ESTING PROGRAM These Surve ill ances ensure that there is a functioning fl O\!V path fro m t he sodium pentaborate solution st orage tan k to t he RPV , including the firing of an explosive valve . The replacement charge for the ex plosive valve shall be fro m the same manufacture d batch as the one fired or fro m another batch that has been certified by havi ng one of that batch successfully fired . The Surveillance may be performed in separate steps to prev ent injecting* boron into the RPV. An acceptable method for verifying, fl ow fro m the pump to the RPV is to pump demineralized water fro m a test tank through one (continued)

HATCH UNIT 2 B 3.140 REVISION

S/RVs B 3.4.3 BASES APPUCABllllY fro m the core until such time that the Residual Heat Re moval (RHR)

(continued) Sy ste m is capable of dissipatingthe oore heat.

In MODE 4, decay heat is low enougrldto ambient conditions of the v alves at no rri nal operating temperatures and pressures. The S/RV setpoint is+/- 3% forOPERABl lU1Y; however, INSERVICE the v alv es are resetto +/- 11% duringithe Surveillance to allow for drift TESTING PROGRAM The Frequency ofthis SR is in accordance with the fnse rvi ee Testin~

~--~ Pr-o~Fa: FR.

(continued)

HATCH UNIT 2 B 14-12 REVISION _ !

ECCS- Operating B 3.5. 1 BASES SURV EILLANCE SR 3.5_ 1.6 (continued)

IREQUfREMENfTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. However, this SR is modified by a Note that stales the Surveillance is only required to be performed prior to entering MODE 2 from MODE 3 or4, when in MOD E 4> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

V erification during or follCJ1111ing MOD E 4 > 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and prior to entering MOD E 2 fro m MOD E 3 or 4 is an excepti on to the normal l'Rsep,iice TestiA§ PFO§Faffl g;eneric v alv e cycling Frequency but is considered acceptable due to the demonstrated reliabil~y of these v alv es . The 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is intended to indicate an outag,e of sufficient duration to allow for scheduling an d proper performance of the Surveillance . If t.he v alv e is inoperable and in the open posit.ion , t.he INSERVICE associatedlPCll subsystem must be d eclare d inoperable .

TESTING PROGRAM SR 3.5.1.7 . SR 3.5.1.8. and SR 3.5.1.9 The performance require ments of the low pressure ECCS pumps are det ermined through application of the 10CFR 50, Appendix K criteria (Ref. 8). This periodic Surveillance is performed (in accordance with the ASM E OM Code require ments for the ECCS pumps) to v erify that the ECCS pumps will dev elop the flow rates required by the respectiv e analy ses . The low pressure ECCS pump flow rates ensure that adequate core cool ing is provided to satisfythe acceptance criteria of Reference 10. The pump flow rat es are v erified against a system head equivalent to the RPV pressure expected during a lOCA. The total system pump outlet pressure is adequate to ov ercome the elevati on head pressure betw een the pump suction and the v essel discharge , the piping friction losses , andRPV pressure present during a LOCA. These v alues may be established during preoperational t estingL The flow tests for th e IHPCI Sy ste m are performed at two different pressure ranges such th at sy stem capability to provide rated flow is t ested at both the higher and lower operatin g ranges of the system.

The pump flow rates are v erifie d against a syste m head corresponding to the RPV pressure. The total sy ste m pump outlet pressure is adequate to overcome the elev ation head pressure between the pump suction and the v essel discharge , the piping friction losses , and IRPV pressure. Addtionally , adequate steam flow mu st be passingthrough the main turbine orturbine bypass v alves to continue to control reactor pressure wh en the HPC! Sy stem div erts steam flow. The reactor steam pressure must be~ 920 psigto perform SR 3.5. 1 . 8and~150 psig to perform SR 3.5.1!.9. Adequate (continued)

HATCH UNIT 2 B 3.5-10 REVI S I ON ~

ECCS - Operating B 3.5. 1 BAS ES SURVEILLANCE SR 3_5_ 1_7. SR 3_5_ 11_8, and SR 3-5.1.9 (continued)

REQUIREMENTS steam flow for SR 3_5_ 11.8 is represented by at least two turbine bypass valves open, or~ 20Qi MWE from t he main turbine-generator, and for SR 3.5.1.9 adequate steam flow is represented by at least 125 turbine bypass valv es open , or total steam flow~ 1E6 lb/ hour_

Therefore , sufficient ti me is allowed after adequate pressure and flow are achiev ed to perform these te sts. Reactor startup is allowed prior to performi ng the low pressure Surveillance test because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance test is short. The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure test has been satisfactorily completed and there is no indication or reason to believ e that lrlPCI is inoperable. Therefor~.

SR 3.5.1.8 and SR 3_5_ 1.9 are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months afterthe reactor steam pressure and flow are adequate to perform the test.

The 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowed is suffioient to achieve stable conditions for testing and provide s a reasonable time to complete the SR.

The Frequency for SR 3.5.1-7 is consistent with the lr1se1vice Testi11g PregFB:m pump testing require ments . The Frequencies for SR 3.5.1.8 and SR 3.5.1_'9 are based on operating experience, equipment reliability , and plant ri sk, and are controlled under the Surveillance Frequency Control Program_

INSERVICE TESTING PROGRAM SR 3.5.1 .10 The ECCS subsy stems are required to actuate automatically to perform their design functions. This Surveillance verifies that, with a required sy stem initiation sign al (actual or simulated), the automatic initiation logic of HPCI, CS , and LPCI will caus e the systems or subsy stems to operat e as designed, including actuation of the system throughout its emerg,ency operating sequence , automatic pu mp startup an d actuation of all automatic valves to their required positions. This SR also ensures th at the HPCI: System will automatically restart on an RPV low water level (Level 2) signal receiv ed subs equent to an RPV high wat er level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The L:OGl.C SYSTE M FUNCTIONAL TESTperformed in lCO 3.3-5. 1 overlaps this Surveillance to provide co mplete testing of the assumed safety function .

(continued)

HATCH UNIT 2 B 3.5-11 REVISION

PCIV s B 3.6.1.3 BASES SURV Elt!J\NCE SR 3 .6 .1!.3.5 (continued}

REQ UIREMENTS closure isolation ti me is demonst rated by SR 3.6 .1.3 .6. The isolation ti me test ensures that each v alv e will isolate in a time period less than or equal to that listed in the FSAR and that no degradation affecting, v alv e closure since the performance of the last surveillance has oocurred. (EFCV s are not required to be tested becau se they hav e no specified ti me limit). The* Frequency of this S R is in accordance with the require ment s of the l'IT':'l"T'!Trr-P--t-i:ir<:t-rnrr""P"rnrnr::rnr-SR 3.6.1.3.6 V erifying that the isolat ion ti me of each MSIV is within the specifie d limits is require d to demonstrate O PERABI LITY. The isolation time test ensures that the MS IV will isolate in a ti me period that does not excee d the ti mes assumed in the OBA analyses . This ensures that the calculated radiological consequences of these ev ents re main within 1,0 CFR 50. 67 limits. Th e Frequency of th is SR is in 1

accordance with the requirements of the l ~eTY-1 . ;e.-il-eST+.R&+'f&e-~R:-

INSERVICE SR 3.6.1.3. 7 TESTING PROGRAM Auto matic PCIV s close on a pri mary contain ment isolation signal to prevent leakage of radioactiv e material fro m primary contain ment followi ng a DBA. This SR ensures th at each automatic PC IV wi ll actuate to its isolation position on a primary containment isolation signal. The LOGIC SYSTE M FUNCTIONAL TE ST in SR 3.3.6.1i.6 ov erlaps this SR to provide co mplete test ing of the safety function .

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.6 .1.3.8 This SR requires a demonstration that each reactor instrumentation line excess flow check.v alv e (EFCV) (of a repre sentativ e sample) is O PERABLE by v erifyi ng that t he v alv e reduces flow t o within li mits on an actu al or simulated instrument line break condition . (The representativ e sample consists of an approximately equal number of EFCV s, such that each EFCV is tested at least once ev ery 10 years

[no minal] . In addition , the EFCV s in the sample are representativ e of the various pl ant configurat ions, model s, siz es , an d operating envi ron ment s. This ensures t hat any potentially co mmon proble m (continued)

HATCH UNIT 2 B 3.6--24 REV ISION

Reactor Building-to-Suppression Chamber Vacuum Breakers B 3_6_1_7 BASES SURVEILl..ANCE SR 3_'6_1_7_1 (continued)

REQUIREMENTS Two Notes are added to this SR The first N'ote allows reactor building-to-suppression chamber vacuu m breakers opened in conj unction with the performance of a Surveillance to not be c onsidered as failing this SR These perio d s of opening vacuu m ~

breakers are controlled by plant procedures an d do not re p resent inop erable*vacuu m breakers. The second N'ote is includ ed to clari fy that vacuum breakers, which are* open due t o an actual differential pressure , are* not cons idered as failing this SR SR J _.S_1I2 Each vacuu m breaker must be cycled to ensure that it opens p roperly to p erfo rm it s design function and returns to its full y close d position_

This ensures that the safety analy sis assumptions are valid. The 92 day Frequency of this SR is in acco rdance with the requ ire ments of the l'nSierviee Testing Program.

INSERVICE TESTING Demonstration of vacuum breaker opening1setpoint is necessary to PROGRAM ensure that the safety analy sis assumption reg:arding v acu um breaker full open differential pressure of::::; 0.5 psid is v ali d. The Su rv eillance Fre quency is controlled under t he Surveillance Frequency Control Program.

REFERENCES 1_ FSAR, Secti on 6.2.1_

2. NRC No. '9J-102, "Final Policy St atement on Technical S p ecificat ion Improv ements," July 23, 1993.
HATCH UNIT 2 B 3_&-41 REVISlON
RHR Suppression Pool Cooling B 3 .6.2.3 BASES SURVEILLANC E SR 3 .6 .2 .3 .2 REQUIREMENTS
{continued) V erify ing1that each required RHR pump develops a flow rate
~ 7700 gpmwhile*operating in the suppression pool ooo ling; mode with flow th rough the associated heat ex changer ensures that pump performance has not degraded during the cycle. Flow is a norm al test of centrifugal pump performance required by ASM E OM Co de (Ref. 2 ). This test oonfirms one point on the pum p design cu rve, an d the res u Its a rein di cative of ove ra II pe rfo rrnan ce*. Su ch ins e rvi ce INSERVICE tests confirm .co mpon entOPERABILITY an d detect inci pient fa ilures by TESTING in dicating1abnormal performance. The Fre quen cy of this SR is in PROGRAM accordance w ith the* lr1se1 virnTesti11g Program REFERENCES 1. FSAR, Section 6 2.2 .
2. ASM E Co de for Operation andMaintenance *of Nuclear Power Plants (OM Code)
3. NR:C No. '93-102 , "'Final Po licy State m ent on Technical S pecification Improvements ," July 23 , 1993 .
HATCHUNIT2 B 3 .6-59 REVI SION
SR Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY
~~~~~~~~~~~~~~~~
SR 3.0.2 and SR 3.0.3 apply in Chapter 5 BASES only when invoked by a Chapter 5
= = = = = = = = = = = = = =4== ==l Specification.
'---'-~~~~~~~~~~~~~~----'
SRs SR 3.0.1 t ough SR 3.0.4 establish the general requirements applicab to all Specifications and apply at all times , unless otherwise stated .
SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for vefiich the req'uirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components , and that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO .
Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in this Specification ,
however, is to be construed as implying that systems or components are OPERABLE when :
a. The systems or components are known to be inoperable, although still meeting the SRs ; or
b. The requirements of the Surveillance(s) are known not to be met between required Surveillance performances.
Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified . The SRs associated with a test exception are only applicable when the test exception is used as an allowable exception to the requirements of a Specification .
Surveillances , including Surveillances invoked by Required Actions ,
do not have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERABLE status .
Upon completion of maintenance appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not fa iled and their most recent performance is in accordance with SR 3.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established . In these situations, the equipment may be (continued)
Vogtle Units 1 and 2 B 3.0-13 Rev. 3 - 9/06
SR Applicability B 3.0 BASES SR 3.0.1 considered OPERABLE provided testing has been satisfactorily (continued) completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed .
SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per . .. " interval.
SR 3.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for When a Section 5.5, conducting the Surveillance (e.g ., transient conditions or other "Programs and ongoing Surveillance or maintenance activities) .
Manuals,"
specification states The 25% extension does not significantly degrade the reliability that that the provisions of results from performing the Surveillance at its specified Frequency.
SR 3.0.2 are This is based on the recogn ition that the most probable result of any applicable, a 25% particular Surveillance being performed is the verification of extension of the conformance with the SRs. The exceptions to SR 3.0 .2 are those testing interval , Surveillances for which the 25% extension of the interval specified in the Frequency does not apply. These exceptions are stated in the whether stated in the individual Specifications. The re *
specification or recedence over the TS . Therefore, vvnen a test interval is speoified incorporated by in tne Fegulations , tne test interval eannot SR 3.0.2 be extended by the reference , is T-S, a11d ti 1e SR i11cludes a Note i11 ti 1e F1 eque1 icy statiJ 19 ti 1at permitted . "SR 3.0.2 is 11ot applicable." An example of an exeeption when the test interval is not speoified in the Feg1:Jlations is the Mote in the Containment Leakage Rate Testing Program , "SR 3.0.2 is not As stated in SR 3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per ... " basis . The 25% extension applies to each performance after the initial performance. The initial performance of the Required Action , whether it is a particular Surveillance or some other remedial action, is considered a single action with a single Completion Time . One reason for not allowing the 25% extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.
Examples of where SR 3.0.2 does not apply are the Containment Leakage Rate Testing Program required by 10 CFR 50, Appendix J, and the inservice testing of pumps and valves in accordance with applicable American Society of Mechanical Engineers Operation and Maintenance Code , as required by 10 CFR 50.55a . These programs establish testing requirements and Frequencies in accordance with the requirements of regulations. The TS cannot, in and of themselves ,
extend a test interval specified in the regulations directly or by reference.
Vogtle Units 1 and 2 B 3.0-14 Rev. 4-9/06
SR Applicability B 3.0 BASES SR 3.0.2 The provisions of SR 3.0 .2 are not intended to be used repeatedly (continued) merely as an operational convenience to extend Surveillance intervals (other than those consistent with Refueling intervals) or periodic Completion Time intervals beyond those specified.
SR 3.0.3 SR 3.0 .3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the When a Section 5.5, specified Frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the "Programs and limit of the specified Frequency, whichever is greater, applies from Manuals," specification the point in time that it is discovered that the Surveillance has not states that the been performed in accordance with SR 3.0.2, and not at the time provisions of SR 3.0.3 that the specified Frequency was not met.
are applicable, it permits the flexibility to This delay period provides adequate time to complete Surveillances defer declaring the that have been missed . This delay period permits the completion of a testing requirement not Surveillance before complying with Required Actions or other remedial met in accordance with measures that might preclude completion of the Surveillance.
SR 3.0.3 when the testing has not been The basis for this delay period includes consideration completed within the of unit conditions , adequate planning , availability of personnel , the testing interval time required to perform the Surveillance, the safety significance of (including the the delay in completing the required Surveillance , and the recognition allowance of SR 3.0.2 if that the most probable result of any particular Surveillance being invoked by the Section performed is the verification of conformance with the requirements .
5.5 specification).
When a Surveillance with a Frequency based not on time intervals, but upon specified unit conditions , operating situations , or requirements of regulations (e.g., prior to entering MODE 1 after each fuel loading , or in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions, etc.) is discovered to not have been performed when specified , SR 3.0.3 allows for the full delay period of up to the specified Frequency to perform the Surveillance.
However, since there is not a time interval specified , the missed Surveillance should be performed at the first reasonable opportunity.
SR 3.0.3 provides a time limit for, and allowances for the performance of, Surveillances that become applicable as a consequence of MODE changes imposed by Required Actions .
Failure to comply with specified Frequencies for SRs is expected to be an infrequent occurrence . Use of the delay period established by SR 3.0 .3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals. While up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or the limit of the specified Frequency is provided to perform (continued)
Vogtle Units 1 and 2 83 .0-15 Rev. 4- 9/06
Pressurizer Safety Valves B 3.4.10 BASES (continued)
ACTIONS With one pressurizer safety valve inoperable, restoration must take place within 15 minutes. The Completion Time of 15 minutes reflects the importance of maintaining the RCS overpressure protection system. An inoperable safety valve coincident with an RCS overpressure event could challenge the integrity of the pressure boundary.
B.1 and B.2 If the Required Action of A.1 cannot be met within the required Completion Time or if two or more pressurizer safety valves are inoperable, the plant must be brought to a MODE in which the requirement does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 4 with any RCS cold leg temperatures the COPS arming temperature specified in the PTLR within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. In MODE 4, with any RCS cold leg temperature s the COPS arming temperature specified in the PTLR ,
overpressure protection is provided by the cold overpressure protection system . The change from MODE 1, 2, or 3 to MODE 4 with any RCS cold leg temperature s the COPS arming temperature specified in the PTLR , reduces the RCS energy (core power and pressure) , lowers the potential for large pressurizer insurges, and thereby removes the need for overpressure protection by three pressurizer safety valves.
SURVEILLANCE SR 3.4.10.1 INSERVICE TESTING PROGRAM REQUIREMENTS ~
SRs are specified in the II 1seniiee Testi119 Pro9r!l11i . Pressurizer safety valves are to be tested in accordance with the requirements of the ASME OM Code (Ref. 4) , which provides the activities and Frequencies necessary to satisfy the SRs. No additional requirements are specified . The lift settings shall be 2 241 O psig and s 2510 psig . The lift setting pressures shall correspond to ambient conditions of the valves at normal operating temperature and pressure.
(continued)
Vogtle Units 1 and 2 B 3.4.10-4 Rev.
COPS B 3.4 .12 BASES (continued)
SURVEILLANCE SR 3.4.12.1 and SR 3.4.12.2 REQUIREMENTS To minimize the potential for a low temperature overpressure event by limiting the mass input capability, both safety injection pumps are verified incapable of injecting into the RCS , and the accumulator discharge isolation valves are verified closed and locked out.
The safety injection pumps are rendered incapable of injecting into the RCS through at least two independent means such that a single failure or single action will not result in an injection into the RCS .
The Surveillance Frequency is controlled under the Surveillance I
Frequency Control Program .
INSERVICE TESTING PROGRAM SR 3.4.12.3 Each required RHR suction relief valve shall be demonstrated OPERABLE by verifying its RHR suction isolation valves are open and by testing it in accordance with the IAserviee TestiAg PrograA'I.
This Surveillance is only required to be performed if the RHR suction relief valve is being used to meet this LCO . For Train A, the RHR suction relief valve is PSV-8708A and the suction isolation valves are HV-8701A and B. For Train B, the RHR suction relief valve is PSV-8708B and the suction isolation valves are HV-8702A and B.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program . The RHR suction valves are verified to be opened. INSERVICE TESTING PROGRAM ti The ASME OM Code (Ref. 8) test per lnservioe Testing PrograA'I verifies OPERABILITY by proving proper relief valve mechanical motion and by measuring and , if required , adjusting the lift setpoint.
SR 3.4.12.4 The RCS vent of 2 1.5 square inches (based on an equivalent length of 10 feet of pipe) is proven OPERABLE by verifying its open condition.
(continued)
Vogtle Units 1 and 2 B 3.4.12-12 REVISION
RCS PIV Leakage B 3.4.14 BASES ACTIONS C.1 (continued) penetration is closed by at least one closed manual or deactivated automatic valve within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . This Action accomplishes the purpose of the interlock.
SURVEILLANCE SR 3.4.14.1 REQUIREMENTS Performance of leakage testing on each RCS PIV or isolation valve used to satisfy Required Action A.1 and Required Action A.2 is required to verify that leakage is below the specified limit and to identify each leaking valve. The leakage limit of 0.5 gpm per inch of nominal valve diameter up to 5 gpm maximum applies to each valve.
Leakage testing requires a stable pressure condition .
The acceptance criteria for RCS PIV leakage is the equivalent of ~ 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure ;;::: 2215 psig and ~ 2255 psig . Test pressures< 2255 psig but> 350 psig are allowed. Observed leakage shall be adjusted for the actual test pressure up to 2235 psig assuming the leakage to be directly proportional to the pressure differential to the one-half power.
For the two PIVs in series, the leakage requirement applies to each valve individually and not to the combined leakage across both valves. If the PIVs are not individually leakage tested , one valve may have failed completely and not be detected if the other valve in series meets the leakage requirement. In this situation , the protection provided by redundant valves would be lost.
Testing is to be performed every 18 months, a typical refueling cycle, if the plant does not go into MODE 5 for at least 7 days. The 18 month Frequency is consistent with 10 CFR 50.55a(f) (Ref. 8) as contained in the IASOF¥ioe Testi A§ Pre§raFA , is within the frequency allowed by the American Societ f Mechanical Engineers (ASME)
OM Code (Ref. 7) , and is based on e need to perform such surveillances under the conditions tha pply during an outage and the potential for an unplanned transient if th urveillance were performed with the reactor at power.
INSERVICE TESTING PROGRAM (continued)
Vogtle Units 1 and 2 B 3.4.14-5 Revision No.
ECCS - Operating 8 3.5.2 BASES SURVEILLANCE SR 3.5.2.2 (continued)
REQUIREMENTS mispositioned are in the correct position . The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .
SR 3.5.2.3 With the exception of the operating centrifugal charging pump, the ECCS pumps are normally in a standby, nonoperating mode. As such , flow path piping has the potential to develop voids and pockets of entrained gases. Maintaining the piping from the ECCS pumps to the RCS full of water ensures that the system will perform properly, injecting its full capacity into the RCS upon demand. This will also prevent water hammer, pump cavitation , and pumping of noncondensible gas (e.g. , air, nitrogen, or hydrogen) into the reactor vessel following an SI signal or during shutdown cooling . The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
lnservice SR 3.5.2.4 Testing Program Periodic surveillance testing of ECCS pumps to detect gross degradation caused by impeller structural damage or other hydraulic component problems is required by the ASME Code OM (Ref. 7) .
This type of testing may be accomplished by measuring the pump developed head at only one point of the pump characteristic curve.
This verifies that the measured performance is within an acceptable tolerance of the original pump baseline performance. SRs are specified in the IAserviee TestiA§ Pre§raffi , hich encompasses the ASME OM Code. The ASME Code provides t ctivities and Frequencies necessary to satisfy the requirements.
In addition to the acceptance criteria of the lnservioe Testin~ Pre ~ rar:n ,
performance of this SR also verifies that pump performance is greater than or equal to the performance assumed in the safety analysis .
Vogtle Units 1 and 2 8 3.5.2-9 Rev.
Containment Isolation Valves B 3.6.3 BASES SURVEILLANCE SR 3.6.3.4 (continued)
REQUIREMENTS misalignment is low. The SR specifies that valves that are open under administrative controls are not required to meet the SR during the time they are open.
Note 1 allows valves and blind flanges located in high radiation areas to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted during MODES 1, 2, 3, and 4 for ALARA reasons. Therefore, the probability of misalignment of these Containment Isolation valves, once they have been verified to be in their proper position , is small.
Note 2 modifies the requirement to verify the blind flange on the fuel transfer canal. This blind flange is only required to be verified closed after the completion of refueling activities when the flange has been replaced for MODE 4 entry and no more fuel transfers between the fuel handling building and containment will occur. The flange is only removed to support refueling operations and once replaced is not removed again until the next refueling . Since the removal of this flange is limited to refueling operations, and access to it is restricted during MODES 1, 2, 3, and 4 , the probability of it being mispositioned between refuelings is small. Therefore, it is reasonable that it be verified once upon completion of refueling activities prior to entering MODE 4 from MODE 5.
SR 3.6.3.5 Verifying that the isolation time of each power operated and automatic containment isolation valve is within limits is required to demonstrate OPERABILITY. The isolation time test ensures the valve will isolate in a time period less than or equal to that assumed in the safety analyses . The isolation time and Frequency of this SR are in accordance with the lnserviee Testing Program . Any change in the scope or frequency of this SR require~ evaluation of STI Evaluation number 417332, in accordance with the urveillance Frequency Control Program .
INSERVICE TESTING PROGRAM (continued)
Vogtle Units 1 and 2 B 3.6.3-11 REVISION
Containment Spray and Cooling Systems B 3.6.6 BASES SURVEILLANCE SR 3.6.6.3 REQUIREMENTS (continued) Verifying that the NSCW flow rate to each pair of units (Fl-1818A & Band Fl-1819A & B) is;::: 1359 gpm provides assurance that the design flow rate assumed in the safety analyses will be achieved (Ref. 4) . The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3.6.6.4 Verifying each containment spray pump's developed head at the flow test point is greater than or equal to the required developed head ensures that spray pump performance has not degraded during the cycle. Flow and differential pressure are normal tests of centrifugal pump performance required by the ASME OM Code (Ref. 6) . Since the containment spray pumps cannot be tested with flow through the spray headers, they are tested on recirculation flow. This test confirms one point on the pump design curve and is indicative of overall performance. Such inservice testing confirms component OPERABILITY, trend performance, and detect incipient failures by abnormal performance. The Frequency of the SR is in accordance with the lnservice Testing Program . INSERVICE TESTING PROGRAM J
In addition to the acceptance criteria of the IAseFViee TestiA!§! Pre!§I FBITl ,
performance of this SR also verifies that pump performance is greater than or equal to the performance assumed in the safety analysis.
SR 3.6.6.5 and SR 3.6.6.6 These SRs require verification that each automatic containment spray valve actuates to its correct position and that each containment spray pump starts upon receipt of an actual or simulated actuation of a containment High-3 pressure signal. This surveillance is not required for valves that are locked, sealed , or otherwise secured in the required position under administrative controls. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program . Any change in the scope or frequency of SR 3.6.6.6 requires reevaluation of STI Evaluation number 417332, in accordance with the Surveillance Frequency Control Program .
(continued)
Vogtle Units 1 and 2 B 3.6.6-8 REVISION
MSSVs B 3.7.1 BASES LCO on allowable THERMAL POWER (to meet ASME Code requirements (continued) and the DBA analysis). These limitations are according to Table 3.7.1-1 in the accompanying LCO , and Required Action A.1 .
The OPERABILITY of the MSSVs is defined as the ability to open within the setpoint tolerances , relieve steam generator overpressure, and reseat when pressure has been reduced . The OPERABILITY of the MSSVs is determined by periodic lift setpoint testing in accordance with the ll"lse"'1iee Testifl§ Pre§raffi .
~ INSERVICE TESTING PROGRAM The lift settings, according to Table 3.7.1-2 in the accompanying LCO ,
correspond to ambient conditions of the valve at nominal operating temperature and pressure.
This LCO provides assurance that the MSSVs will perform their designed safety functions to mitigate the consequences of accidents that could result in a challenge to the RCPB .
APPLICABILITY In MODE 1above31% RTP, the number of MSSVs per steam generator required to be OPERABLE must be according to Table 3.7.1-1 in the accompanying LCO. Below 31% RTP in MODES 1, 2, and 3, only two MSSVs per steam generator are required to be OPERABLE.
In MODES 4 and 5, there are no credible transients requiring the MSSVs. The steam generators are not normally used for heat removal in MODES 5 and 6, and thus cannot be overpressurized ;
there is no requirement for the MSSVs to be OPERABLE in these MODES .
ACTIONS The ACTIONS table is modified by a Note indicating that separate Condition entry is allowed for each MSSV.
A.1 and A.2 With one or more MSSVs inoperable, reduce power so that the available MSSV relieving capacity meets Reference 2 requirements for the applicable THERMAL POWER.
(continued)
Vogtle Units 1 and 2 B 3.7.1-3 Revision No.
MSSVs B 3.7.1 BASES ACTIONS A.1 and A.2 (continued) moderator temperature coefficient, the reduced high flux trip setpoint also ensures that the reactor trip occurs early enough in the loss of load/turbine trip event to limit primary to secondary heat transfer and preclude overpressurization of the primary and secondary systems.
To calculate this power level , the governing equation is the relationship q = m Llh, where q is the heat input from the primary side, m is the steam flow rate, and Llh is the heat of vaporization at the steam relief pressure (assuming no subcooled feedwater). The algorithm used is consistent with the recommendations of the Westinghouse Nuclear Safety Advisory Letter, NSAL-94-001 , dated January 20, 1994 (Ref. 4) . Additionally , the calculated values are reduced by 9% to account for instrument and channel uncertainties.
B.1 and B.2 If the reactor power or the Power Range Neutron Flux-High Trip Setpoints cannot be reduced as required in Table 3.7.1-1 within the associated Completion Time, or if one or more steam generators have four or more MSSVs inoperable per steam generator, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.7.1.1 REQUIREMENTS This SR verifies the OPERABILITY of the MSSVs by the verification of each MSSV lift setpoint in accordance with the lnservioe Test
.ALF0Etfai:R and applicable ASME OM Code (Ref. 5) requirements . The ASME OM Code specifies the necessary test activities and test intervals. As a minimum, the testing will include:
INSERVICE TESTING PROGRAM (continued)
Vogtle Units 1 and 2 B 3.7.1-5 Revision No.
MS IVs 8 3.7.2 BASES SURVEILLANCE SR 3.7.2.1 (continued)
REQUIREMENTS The Frequency is in accordance with the lnservice Testing Program .
Operating experience has shown that these components usually pass the Surveillance when performed in accordance with the lnservice Testing Prograrn .~efore , the Frequency is acceptable from a reliability standpoint. INSERVICE TESTING PROGRAM This SR is modified by a Note that allows entry into and operation in MODE 3 prior to performing the SR. If desired, this allows a delay of testing until MODE 3, to establish conditions consistent with those under which the acceptance criterion was generated.
REFERENCES 1. FSAR, Section 10.3.
2. FSAR, Section 6.2.
3. FSAR, Subsection 15.1 .5.
4. FSAR, Subsection 15.4.9.
5. FSAR, Subsection 15.2.8.
6. 10 CFR 100.11.
7. ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code).
Vogtle Units 1 and 2 8 3.7.2-7 Revision No.
MFIVs and MFRVs and Associated Bypass Valves B 3.7.3 BASES ACTIONS D.1 (continued)
The term isolation system as used in this Condition consists of an MFIV and associated bypass valve or an MFRV and associated bypass valve . An OPERABLE system may include inoperable valve(s) provided the inoperable valves are closed and deactivated . This is acceptable since the closed isolation valve(s) are performing their intended safety function . Since the MODE of Applicability excepts valves that are closed and deactivated , the LCO is no longer applicable to those valves .
E.1 and E.2 If the MFIV(s) and MFRV(s) and the associated bypass valve(s) cannot be restored to OPERABLE status , or closed , or iso lated within the associated Completion Time , the unit must be placed in a MODE in which the LCO does not apply. To achieve this status ,
the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The allowed Completion Time is reasonable , based on operating experience , to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems .
SURVEILLANCE SR 3.7.3.1 REQUIREMENTS This SR verifies that the closure time of each MFIV, MFRV, and associated bypass valves is :5 5 seconds on an actual or simulated actuation signal. The MFIV and MFRV closu re times are assumed in the accident and containment analyses . This Surveillance is normally performed upon returning the unit to operation following a refueling outage .
Th is surveillance is modified by a Note that allows entry into and operation in MODE 2 prior to perform ing the SR .
The Frequency for this SR is in accordance with th e lnservise Testing Progran::i . Operating experience has shown that these components usually pass the Surveillance when performed in accordance with the I nservioe Testing Prog ran::i .
/
INSERVICE TESTING PROGRAM
/
(continued)
Vogtle Units 1 and 2 B 3.7.3-6 Revision No.
AFW System B 3.7.5 BASES (continued)
SURVEILLANCE SR 3.7.5.1 REQUIREMENTS Verifying the correct alignment for manual , power operated , and automatic valves in the AFW System water and steam supply flow paths provides assurance that the proper flow paths will exist for AFW operation . The correct position is the position of the valves necessary to support the operational needs of the plant at that time, including during low power operation and surveillance testing , provided that the requirements of the Technical Specification safety analysis are met. This SR does not apply to valves that are locked , sealed , or otherwise secured in position ,
since they are verified to be in the correct position prior to locking ,
sealing , or securing. This SR also does not apply to valves that
cannot be inadvertently misaligned , such as check valves. This Surveillance does not require any testing or valve manipulation ;
rather, it involves verification that those valves capable of being mispositioned are in the correct position .
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .
SR 3.7.5.2 Verifying that each AFW pump's developed head at the flow test point is greater than or equal to the required developed head ensures that AFW pump performance has not degraded during the cycle. Flow and differential head are normal tests of centrifugal pump performance required by the ASME OM Code (Ref. 2) . Because it is undesirable to introduce cold AFW into the steam generators while they are operating , this testing is performed on recirculation flow. This test confirms one point on the pump design curve and is indicative of overall performance. Such inservice tests confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance . Performance of inservice testing as discussed in the ASME OM Code (Ref. 2) (only required at 3 month intervals) satisfies this requirement. The 31 day frequency on a STAGGERED TEST BASIS results in testing each pump once every 3 months, as required by Ref. 2.
In addition to the acceptance criteria of the lnserviee Testing Program , performance of this SR also verifies that pump I
performance is greater than or equal to the performance assumed in the safety analysis.
INSERVICE TESTING PROGRAM (continued)
Vogtle Units 1 and 2 B 3.7.5-7 REVISION
UHS B 3.7.9 BASES SURVEILLANCE SR 3.7.9.3 (continued)
REQUIREMENTS It also ensures that fan or motor failure , or excessive vibration ,
can be detected for corrective action . The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3.7.9.4 The verification of NSCW basin transfer pump operation includes testing to verify the pump's developed head at the flow test point is greater than or equal to the required developed head . Flow and differential head are normal tests of centrifugal pump performance required by the ASME OM Code (Ref. 3) . This test confirms one point on the pumps design curve and is indicative of overall performance. Such inservice tests confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. The performance of this surveillance in accordance with the lnseP1ioe Testing Program satisfies the requirements of Ref. 3. /
INSERVICE TESTING PROGRAM SR 3.7.9.5 With one tower fan/spray cell out-of-service this SR verifies that ambient wet-bulb temperature remains within the three fan/spray cell region specified in Figure 3.7.9-1 so that the NSCW system remains capable of performing its design basis function.
Requiring this SR when forecasted temperature is > 48 °F provides assurance that the ambient wet-bulb temperature specified in Figure 3.7.9-1 will not be exceeded while the fan is out-of-service. The 24-hour frequency is sufficient since the daily peak temperature is expected to occur once in a 24-hour interval.
Measurement of the ambient wet-bulb temperature should be made, near the time when the daily peak temperature is expected to occur, with a psychrometer in an open area away from sources of moisture, heat or wind , and within the owner-controlled area at Plant Vogtle .
REFERENCES 1. FSAR , Subsection 9.2.5.
2. Regulatory Guide 1.27.
3. ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) .
Vogtle Units 1 and 2 B 3.7.9-5 REVISION
Joseph M. Farley Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, "TS lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing," and to Request an Alternative to the ASME Code Enclosure 5 Description and Assessment of the Proposed Alternative to the ASME Code
Enclosure 5 to NL-16-0091 Description and Assessment of the Proposed Alternative to the ASME Code DESCRIPTION AND ASSESSMENT OF THE PROPOSED ALTERNATIVE TO THE ASME CODE FOR JOSEPH M. FARLEY NUCLEAR PLANT - UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2 Requested in Accordance with 10 CFR 50.55a(z)(2)
Alternative Due To Hardship Without a Compensating Increase in Quality and Safety
1.0 DESCRIPTION
The request is to adopt a proposed alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code by adoption of approved Code Case OMN-20, "lnservice Test Frequency" for use at the Joseph M. Farley Nuclear Plant - Units 1 and 2 (FNP) and at the Vogtle Electric Generating Plant - Units 1 and 2 (VEGP).
2.0 ASSESSMENT Technical Evaluation of the Proposed Alternative to the OM Code Section IST of Division 1 of the OM Code, which is incorporated by reference in 10 CFR 50.55a(a) , specifies component test frequencies based either on elapsed time periods (e.g ., quarterly, 2 years) or on the occurrence of a plant condition or event (e.g., cold shutdown, refueling outage).
ASME Code Case OMN-20, "lnservice Test Frequency," has been approved for use by the ASME OM committee as an alternative to the test frequencies for pumps and valves specified in ASME OM Division: 1 Section IST 2009 Edition through OMa-2011 Addenda, and all earlier editions and addenda of ASME OM Code.
Code Case OMN-20 is not referenced in the latest revision of Regulatory Guide 1.192 (August 2014) as an acceptable OM Code Case to comply with 10 CFR 50.55a(f) requirements as allowed by 10 CFR 50.55a(b)(6) . The proposed alternative is to use Code Case OMN-20 to extend or reduce the IST frequency requirements for the current FNP and VEGP 1O year IST intervals or until OMN-20 is incorporated into the next revision of Regulatory Guide 1.192.
ASME Code Components Affected The Code Case applies to pumps and valves specified in ASME OM Division: 1 Section IST 2009 Edition through OMa-2011 Addenda and all earlier editions and addenda of ASME OM Code. Frequency extensions may also be applied to accelerated test frequencies (e.g. , pumps in Alert Range) as specified in OMN-20.
For pumps and valves with test periods of 2 years of less, the test frequency allowed by OMN-20 and the current TS lnservice Testing Program (as modified by SR 3.0.2 and EGM 2012-001) are the same. For pumps and valves with test frequencies greater than 2 years, OMN-20 allows the test frequency to be extended by 6 months. The current TS lnservice Testing Program does not allow extension of test frequencies that are greater than 2 years.
E5-1
Enclosure 5 to NL-16-0091 Description and Assessment of the Proposed Alternative to the ASME Code
Applicable Code Edition and Addenda
ASME Code Case OMN-20 applies to ASME OM Division : 1 Section IST 2009 Edition th rough OMa-2011 Addenda and all earlier editions and addenda of ASME OM Code.
The FNP Code Edition and Addenda that are applicable to the program interval are OM Code 2001 through OMb-2003 addenda. The FNP current interval ends 11/30/2017.
The VEGP Code Edition and Addenda that are applicable to the program interval are OM Code 2001 through OMb-2003 addenda. The VEGP current interval ends 5/31 /2017.
Applicable Code Requirement
This request is made in accordance with 10 CFR 50.55a(z)(2) , and proposes an alternative to the requirements of 10 CFR 50.55a(f), which requires pumps and valves to meet the test requirements set forth in specific documents incorporated by reference in 10 CFR 50.55a(a).
ASME Code Case OMN-20 applies to Division 1, Section IST of the ASME OM Code and associated addenda incorporated by reference in 10 CFR 50.55a(a).
Reason for Request
The IST Program controls specified in Section 5.5 of TS provide: a) a table specifying certain IST frequencies; b) an allowance to apply SR 3.0.2 to inservice tests required by the OM Code and with frequencies of two years or less; c) an allowance to apply SR 3.0.3 to inservice tests required by the OM Code ; and d) a statement that, "Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS. " In Regulatory Issue Summary (RIS) 2012-10, "NRC Staff Position on Applying Surveillance Requirement 3.0.2 and 3.0.3 to Administrative Controls Program Tests ," and Enforcement Guidance Memorandum (EGM) 2012-001 , "Dispositioning Noncompliance with Administrative Controls Technical Specifications Programmatic Requirements that Extend Test Frequencies and Allow Performance of Missed Tests," the NRC stated that items b, c, and d of the TS IST Program were inappropriately added to the TS and may not be applied (although the EGM allows licensees to continue to apply those paragraphs pending a generic resolution of the issue).
In RIS 2012-1 O and EGM 2012-001, the NRC stated that the current TS allowance to apply SR 3.0.2 and SR 3.0.3 to the lnservice Testing Program would no longer be permitted. In response , OMN-20, which provides allowances similar to SR 3.0.2, was approved and is proposed to be used as an alternative to the test periods specified in the OM code . The proposed alternative substitutes an approved Code Case for the existing TS requirements that the NRC has determined are not legally acceptable as a TS allowance. This proposed alternative provides an equivalent level of safety as the existing TS allowance, while maintaining consistency with 10 CFR 50.55a and the ASME OM Code.
Proposed Alternative and Basis for Use The proposed alternative is OMN-20, "lnservice Test Frequency," which addresses testing periods for pumps and valves specified in ASME OM Division 1, Section IST, 2009 Edition through OMa-2011 Addenda, and all earlier editions and addenda of ASME OM Code.
This request is being made in accordance with 10 CFR 50.55a(z)(2), in that the existing E5-2
Enclosure 5 to NL-16-0091 Description and Assessment of the Proposed Alternative to the ASME Code requirements are considered a hardship without a compensating increase in quality and safety for the following reasons:
1) For IST testing periods up to and including 2 years , Code Case OMN-20 provides an allowance to extend the IST testing periods by up to 25%. The period extension is to facilitate test scheduling and considers plant operating conditions that may not be suitable for performance of the required testing (e.g. , performance of the test would cause an unacceptable increase in the plant risk profile due to transient conditions or other ongoing surveillance, test or maintenance activities). Period extensions are not intended to be used repeatedly merely as an operational convenience to extend test intervals beyond those specified. The test period extension and the statements regarding the appropriate use of the period extension are equivalent to the existing TS SR 3.0.2 allowance and the statements regarding its use in the SR 3.0.2 Bases. Use of the SR 3.0.2 period extension has been a practice in the nuclear industry for many decades and elimination of this allowance would place a hardship on SNC when there is no evidence that the period extensions affect component reliability.
2) For IST testing periods of greater than 2 years, OMN-20 allows an extension of up to 6 months. The ASME OM Committee determined that such an extension is appropriate.
The 6-month extension will have a minimal impact on component reliability considering that the most probable result of performing any inservice test is satisfactory verification of the test acceptance criteria. As such, pumps and valves will continue to be adequately assessed for operational readiness when tested in accordance with the requirements specified in 10 CFR 50.55a(f) with the frequency extensions allowed by Code Case OMN-20.
3) As stated in EGM 2012-001 , if an lnservice Test is not performed within its frequency, SR 3.0.3 will not be applied. The effect of a missed lnservice Test on the Operability of TS equipment will be assessed under the licensee's Operability Determination Program.
Duration of Proposed Alternative The proposed alternative is requested for the current 10 year FNP and VEGP IST intervals or until Code Case OMN-20 is incorporated into a future revision of Regulatory Guide 1.192, referenced by a future revision of 10 CFR 50.55a, whichever occurs first. Currently, FNP is in its fourth interval and VEGP is in its third interval. Note that since VEGP's fourth interval begins June 1, 2017, a separate SNC letter (NL-16-1292) contains a similar Alternative for the VEGP fourth interval.
Precedents The NRC approved the use of OMN-20 for North Anna Power Station on March 27, 2014 (NRC ADAMS Accession Number ML14084A407).
E5-3

v t e Letter Sequence Request
CAC:MF8210, TS Inservice Testing (IST) Program Removal (Approved, Closed) CAC:MF8182, TS Inservice Testing (IST) Program Removal (Open)
Initiation Request Acceptance Supplement Administration Questions Answers Results Approval Other: ML16264A321
MONTHYEAR2016-09-01 [Table View]

NL-16-0091, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application.

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NL-16-0091, License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application.

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Enclosures:

1.0 DESCRIPTION

3.0 REGULATORY ANALYSIS

1.0 DESCRIPTION

Applicable Code Edition and Addenda

Applicable Code Requirement

Reason for Request

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