Text

License Amendment Request to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice 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 Nuclear Licensing Manager July 28, 2016 Southern Nuclear Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.5998 Fax 205.992. 7601 Docket Nos.: 50-348 50-321 50-424 50-364 50-366 50-425 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 SOUTHERN II..\\

NUCLEAR A SOUTHERN COMPANY NL-16-0091 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 1 O 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 1 O 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 1 O 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 Z.. '1/1 1

" day of ::JU 4 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)

, 2016.

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 Basis for Proposed Change to NL-16-0-091 Basis for Proposed Change 1.0 Description 2.0 Assessment 3.0 Regulatory Analysis Table of Contents 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 Applicability 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 1 O 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 1 O 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 1 O 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 1 O 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 FNP, HNP, and VEGP Technical Specification Marked Up Pages

1.1 Definitions ENGINEERED SAFETY FEATURE (ESF) RESPONSE TIME LEAKAGE INSERVICE TESTING PROGRAM Farley Units 1 and 2 The ESF RESPONSE TIME shall t>e that time interval from when the monitored parameter exceeds its ESF actuation

.setpoint at the channel sensor until the ESF equipment is

,capable-of performing its safetyfunction (i.e., the valves trave I to their required pas iti ons. pump dis charge press ure.s reach their requiredvalues, 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 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 conductedtocollection systems or a sump or collecting tank;

2.

LEAKAGE into the containment atmospherefrom 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 thmugh 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; The INSERVICE TESTING PROGRAM is the licensee program that fulfills the requirements of 10 CFR 50.55a(f).

1.1-3 (continued)

Amendment No. 1-4-9 (Unit 1)

Amendment No. ttt- (Unit 2)

Pressurizer Safety Valves 3-4.10 SURVEILLANCE REQUIREMENTS SR 3.4.1:0.1 SURVEILLANCE Verify each pressurizer safety valve is OPERABLE in accordance with the IAser.*iee TestiA§ PFO§Faffl.

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

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

Amendment No. 1 (Unit 2)

~ St.JRVEl lJANCE REQUIREMENfTS SURVEILLANCE SR 3.4.12.1:

Verify a maximum of one charging pump is capable of injecting into the RCS when one or more RCS cold legs is 5: 180F.

SR 3.4.12.2 Verify a maximum of two charging pumps are capable of injecting into the RCS when all RCS cold legs are> 180F.

SR 3.4.12.3 V erify each accumulator is isolated.

SR 3.4.12.4 Verify RHR suction isolation valves are open for each required RHR suction relief valve.

SR 3.4.12.5

-NOTE------ ------ - --

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

Verify RCS v ent~ 2.85 square inches open.

SR 3.4.12.'6 Verify each required RHR suction relief valve setpoint.

(:sERVICE TESTING PROGRAM LTOP System 3.4.12 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance f requency Control Program ln accordance with the Surveillance Frequency Control Program ln accordance with the frrnel"1'iee TestiR§ Pffi§ffim

"?!

AND In accordance with the Surveillance Frequency Control Program c:

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

Amendment No. 1-89-(Unit 2)

ECCS-Operating 3_5_2 SURVEILLANCE REQUIREMENTS SR 3_5_2_1 SR 35-2-2 SR 3-5.2-3 SR 3-5.2-4 SURVEILLANCE

- - NOTE----- --- - ---

Only required to be performed: forv alves 8132A and 81328 when Centrifugal Charging1 Pump A is inoperable_

V erify the followin9 valve*s are in the listed position with powerto the valve operator removed_

Number Position 8884, 8886 Closed 8132A, 81328 Open 8889 Closed Function Centrifugal Charging Pump to IRCS Hot Leg Centrifugal Charging Pump discharge isolation RHR to RCS Hot Leg [nj ection V erify each ECCS manual, power operated, and automatic valve in the flow path, that is not loc ed.

sealed, or otherwise secured in position, is in the correct position_

V erify each ECCS pump's develop ed he*ad at the test flow point is greater than or equal to the required developed head_

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the lflserviee 11 Te3ting, Program V erify each ECCS automatic valve in the flow path Ln accordance with that is not locked, sealed, or otherwise secured in 1 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 Amendment No_ +as- (Unit 1)

Amendment No_ "IB6- (Unit 2}

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SR 3_6_3_3 SR 3.6.3.4 SR 3.6.3-5 SR 3_6_3_6

1.

SURVEILLANCE NOTES------------- --

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 blind flange that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls_

Verify the isolation lime of each power operated or automatic containment isolation valve in the-fSf-Progran1 is within limits_

Perfo leakage rate testing for containment penet tions containing containment purge valves with re *1ient seals_

Verify each automatic containment isolation valv e that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

FREQUENCY Prior to enterin9 MODE 4 from MODE 5 if not performed within the previous 92 days n accordance with the Surveillance Frequency Control Program AND Within 92 days after openingi the valve In accordance with the Surveillance Frequency Control 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 SURVEILlANCE REQUIREMENTS

\\

SURVEILLANCE

\\

FREQUENCY SR 3.6.6.4 Verify each containmen~ s~ray pump's developed \\

In accordance with head at the flow test point 1s greaterthan or equal to, J the IAseF't'iee the required developed head_

+estiR§ PFe§F<Ht:t 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 secure di 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. 1 (Unit 1)

Amendment No. 100- (Unit 2)

ACTIONS CONDITT ON REQUIRED ACTION

8.

(continued) 8.2

-NOTE------

Only required in MODE 1.

Reduce the Power Range 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 MSSVs.

C.

Required Action and c.1 1

Be in MODE 3.

associated Completion Time not met.

AND OR C.2 Be in MODE 4.

One or more steam generators with ~ 4 MSSV s inoperable.

SURVEILLANCE REQUIREMENTS SR 3.7.1.1 SURVEILLANCE

-NOTE- - - ----- -----

Only required to be performed in MODES 1 and 2.

Verify each required MSSV Ii.ft setpoint per Table

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

+/-1:%.

MSSVs 3.7.1 COMPLETION TIME 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 6 hours 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months FREQUENCY In accordance with the ll'lserviee Testing Progran1 Farley Units 1 and 2 3 7.1-2 Amendment No. T46- (Unit 1)

Amendment No 1-3-t-- (Unit 2)

ACTIONS CONDITION E_ One or more steam lines E_1i with two MSIV s inoperable in MODE 2 or3_

F_ Required Action and f _1 associated Completion Time of Condition D or E AND not met F-2 SURVEILLANCE REQUIREMENTS REQUIRED ACTION Verify one MSIV closed in affected steam line_

Be in MODE 3.

Be in MODE 4_

MS IVs 3.7_2 COMPLETION TIME 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Once per 7 days thereafter 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours SllRVEIU.ANCE FREQUENCY SR 3_7_2_1 NOTE-- ---- ----- ---

Only required to be performed in MODES 1 and 2.

Verify closure time of each MSIV is :5 7 seconds_

In accordance with the 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 bypass valves valve.

inop erable.

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

0.

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.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months associated Completion Time not met SIURVEll lANCE REQUIREMENTS SR 3.7.3.11 SURVEILLANCE Verify the closure time of each Main FW Stop Valve, MFIRV, and associated bypass valve is in accordance with the time requirement in the IMef'o'iee Testil'lg.

~

FREQUENCY In accordance with the ll'lsel"o'iee Testil'lg Program.

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

Amendment No. Bl- (Unit 2)

AFW System 3_7_5 SURVEILLANCE REQUIREMENTS SR 3.7-5.2 SR 3-7_5_3 SR 3_7_5_4 SR 3.7-5.5 SURVEILLANCE

-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 the developed head of each AFW pump at the flow test point is greaterthan or equal to the required developed head_

Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position. actuates to the correct position on an actual or simulated actuation signal.

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 actual or simulated actuation signal.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Verify the turbine driven AFW pump steam admission l'n 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 TS5- (Unit 1)

Amendment No_ too- (Unit 2)

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Reactor Coolant Pump Flywheel l'nspection Program (continued) 5.5.8

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.J. are applicable to the Reactor Coolant Pump Flywheel Inspection Program.

~ J

~

Not Used

--+iln~s~E!>f' f\\.ttiif" e,..e -tc T~e~stm i nwgr PI-'; ff fOW'9tt';ffijt1ffiFfl1-This program provides controls for inservice testing of ASME Code Class 1, 2, a

1 3 components. The program shall include the following1:

a.

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

ASME B

er and Pressure Vessel Cod nd applicable Ad da terminology for inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 onths Every 9 months Yearly or annually Biennially orev 2 years quired Frequencies for performing in service testing activities At least once per 7 days At least once per 31 days At least once per 92 days At least once per184 days At least once per276 days

east once per 366 days Al le t once per 731 days

b.

The provi

ons of SR 3.0.2 are applicable to the above 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 and Pressure Vessel Code shall be cons to supersede the requirements of any TS.

5.5.9 Steam Generator (SG} Program A Steam Generator Program shall be established and implemented to ensure that SGtube integrity is maintained. tn add1tion, the Steam Generator Program shall include the following1:

a.

Provisions for condition monitoring assessments. Condition monitoring Farley Units 1 and 2 5.5-5 (continued)

Amendment No. 1-9Z-(Unit 1)

Amendment No. ffit}-(Unit 2)

Definitions 1.1 1.11 Definitions (continued)

The INSERVICE TESTING PROGRAM is the licensee program that fulfills the requirements of 1 O CFR 50.55a(f).

END OF CYCLE RECllRCUl.A TION PUMP TRIP (EOC-RPT)

SYSTEM RESPONSE TIM E INSERVICE TESTING PROGRAM LINEAR HEAT

GENERAl!ON RATE l.cOG!C SYSTEM FUNCTIOl\\Y\\l TEST HATCH UNIT 1 The EOC-RPT SYSTEM RESPONSE TIME shall be that time interval from initial signal generation by the associated turbine* stop valve limit switch or from when the turbine control valve hydraulic control oil pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts ofthe 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.

LEAKAGE shall be:

a.

Identified LEAKAGE 1i.

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 leakag,e 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 GENERATION RATE (LHGR} shall be the powerg:eneration in an arbitrary length of fuel rod, usually six inches. ll is the integral of the heat flux over the heat transfer area associated with the unit length_

A LOG[C SYSTEM FUNCTIONAL TEST shall be a test of all required logic components (i.e., all required! relays and contacts, trip 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 OPERABILlifY_ 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_

1.1-3 (continued)

Amendment No. ~

SLC System

/.:~--~

3. 1. 7

\\_'NSERVICE TESTING PROGRAM SURVEILLANCE REQUIREMENTS (continued)

SR 3.1.7.7 SR 3.1.7.8 SR 3.1.7.9 SR 3.1.7.1'0 HATCH UNIT 1 SURVEILLANCE FREQUENCY V erify each pump develops a flow rate:<! 41.2 gpm at a discharge pressure~ 1232 psig.

Verify flow through one SLC subsystem from pump into reactor pressure vessel.

Verify all heat traced piping between storage tank and pump suction is unblocked.

Verify sodium pentaborate enrichment is

~ 60.0 atom percent B-10.

3.1-20 In accordance j with the lnservice Testing Program In accordance with the Surveillance Fr!)quency Control Program In accordance with 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 Prior to addition to SLC tank Amendment No. ~

SURVEILLANCE REQUIREMENTS SR 3.4.3.1 HATCH UNIT 1 SURVEILLANCE Verify the safety function lift setpoints of the S/RVs are as follows:

Number of S/RVs 11 Setpoint

{Qfilg) 1150< +/- 34.5 Following testing, lift settings shall be within+/- 1%..

3 4-6 S/RVs 3.4.3 FREQUENCY In accordance with the l'r-,seroo ice Te!lting Progra:n1 Amendment No.~

SURVEILLANCE REQUIREMENTS continued SR 3.5.1.6 SR 3.5.1.7 SR 3.5.1.8 HATCH UNIT 1 SURVElllANCE

-NOTE-- ------ ----

Only required to be performed prior to entering:

MODE 2 from MODE 3 or4, 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 cycles through one complete cycle of full travel or is de-energ,ized in the closed position.

Verify the following EGGS pumps develop the specified flow rate ag1ainst a system head corresponding to the specified reactor pressure.

SYSTEM HEAD CORRESPONDING NO.OF TOAREACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF cs LPCI 2. 4250 g:pm 1

2 17,000 gpm 2

~ 113 psig 2

20 psig

-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~ 1!058 psig and

~ 920 psig, the HPCI pump can develop a flow rate ~ 4250 gpm against a system head corresponding to reactor pressure.

3.5-4 ECCS - Operating 3.5.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In aocordance with the Surveillance Frequency Control Program (continued)

Amendment No....26.6.

SURVEILLANCE REQUIREMEN!fS continue SR 3_5_2-3 SR 3.5.2.4 SR 3.5.2.5 SR 3.5.2.6 HATCH UNIT 1 SURVEILLANCE Verify. for each required ECCS injection/ spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

-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 subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

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

SYSTEM HEAD CORRESPONDING NO.OF TOA.REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF cs LPCI 24.250gpm 2 7700gpm 1

1

"'113 psig 2

.20psig NOTE-------------

Vessel injection/spray may be excluded.

Verify each required EOCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.

INSERVICE TESTING PROGRAM 3.5-8 ECCS - Shutdown 3_5_2 FREQUENCY In accordance with the Surveillance Frequency Control Program l'n accordance with the Surveillance Frequency Control Program In accordance with the lnservice lestiAg PFOgram l'n accordance with the Surveillance Frequency Control Program Amendment No.-:2£&

SURVEIU.ANCE REQUIREMENTS continued SR 3.6.1.3.2.

SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.5 HATCH UNIT 1

1.

2.

SURVEILLANCE NOTES-----------

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

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

Verify each primary containment isolation manual valve and blind flange that is located outside primary containment and is required to be closed during accident conditions is closed.

1.

2.

NOTES----- - -----

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

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

Verify each primary containment manual isolation valve and blind flange that is located inside primary containment and is required to be closed during accident conditions is closed.

Verify continuity of the traversing in core probe (flP) shear isolation valve explosive charge.

Verify the isolation time of each power operated and each automatic PCIV, except for MSIVs, is within limits.

INSERVICE TESTING PROGRA 3.S-11 PCIVs 3.6.1.3 FREQUENCY In accordance with the Surveillance Frequency Control Program Priorto entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within. the previous 92 days In accordance with the Surveillance Frequency Control Program l'n accordance with the IRseFViee TestiA§ PFO§Fam (continued)

Amendment No. Z6'6-

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.6.1'.3.6 Verify the isolation time of each MSIV is

~ 3 seconds and~ 5 seconds.

0NSERVICE TESTING PROGRAM\\-

SR 3.6.1.3. 7 Verify each automatic PCIV, excluding EFCVs, actuates to the isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.8.

Verify each reactor instrumentation line EFCV (of a representative sample) actuates to restrict flow to within limits.

SR 3.6.1.3.9 Remove and test the explosive squib from each shear isolation valve of the TIP system.

SR 3.6.1.3.10 Verify combined MSl<V leakage rate for all four main steam lines is~ 100 scfh when tested at

~ 28.0 psig and < 50.8 psig.

OR Verify combined MSIV leakage rate for all four main steam lines is~ 1i44 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 to the fully closed and fully open position_

SR 3.6.1.3.13 Verify the combined leakage rate for all secondary containment bypass leakage paths is~ 0.02 La when pressurized to~ Pa.

HATCH UNIT 1 3 6-12 PCIVs 3.6.1.3 FREQUENCY rn accordance with the ll'lse!'Viee festing Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Primary Containment Leakage Rate Testing Program In accordance with the Surveillance Frequency Control Program In accordance with the Primary Containment Leakage Rate Testing Program Amendment No.--260

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

CONDITION IREQUllRED ACTl:ON E.

Required Action and Associated Completion Time not met E.1 Be in MODE 3.

Be in MODE 4.

SURVEILLANCE REQUIREMENTS SR 3.6.1.7.1 SR 3.6.1. 7.2 SR 3.6.1.7.3 HATCH UNIT 1

1.

2.

SURVEILLANCE NOTES--- -------

Not required to be met for vacuum breakers lha1 are open during Surveillances.

Not require di to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is dosed.

Perform a functional test of each vacuum breaker.

Verify the opening setpoint of each vacuum breaker is

.~ 0.5 psid.

3.6-18 COMPLETION TlME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours FREQUENCY In accordance with the Surveillance Frequency Control Program l'n accordance with the lnservise Testing Pmgr:am l'n accordance with the Surveillance Frequency Control Program Amendment No."'Z"6'6"

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.i6.2.3.2 Verify each required RHR pump develops 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 Amendment No.~

5.5 Programs and Manuals (continued) 5.5_5 Component Cyclic or Transient limit Programs and Manuals 5.5 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 ASME Code Class 1, 2, components including applicable supports_

a_

Te ing frequencies specified in Section XI of the ASME Baile Pres e Vessel Code and applicable Addenda are as foll ASME Baile nd Pressure Vessel Code a 1 Applicable Addenda Termino for lnservice Testin Weekly Monthly Quarterly or every 3 months Semiannually or every 6 nths Yearly or.annually Required requencies for Pe arming lnservice Te n Activities 7 days 31r days At least once per 92 days t least once per 1i84 days A, ast once per366 days b_

The provisions

SR 3.0.2 are applicable to the performing i ervice testingi activities; c _

The P, visions ofSRJ..0.3 are applicable to inservice test1 an Nothing' in the ASME Boiler and Pressure Ves.sel Code shall be con to supersede the requirem ents of any Technical Specification_

5.5_7 Ventilation Filter Testing Program (VFliP)

The VRP will establish the required testin9 of Engineered Safety Feature (ESF) filter ventilation systems 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 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 11_ 1 Definitions (continued)

EMERGENCY CORE COOLING SYSTEM (ECCS)

RESPONSE

TlME END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RP1)

SYSTEM RESPONSE TIME ISOLATION SYSTEM RESPONSE TIME LEAKAGE INSERVICE TESTING PROGRAM HATCH UNIT 2 The ECCS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS initiation setpoint at the channel sensoruntil the ECCS 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_

The EOC-RPT SYSTEM RESPONSE TIME shall be that time interval from initial signal generation by the associated turbine stop valve limit switch or from when the turbine control valve hydraulic control oil pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts of the 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_

The ISOl..A TfON! SYSTEM RESPONSE TIME shall be that time interval from when the monitored' parameter exceeds its isolation initiation 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_

LEAKAGE shall be:

a.

Identified LEAKAGE

1.

LEAKAGE into the drywell, such as that from pump seals or valve 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 LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE; The INSERVICE TESTING PROGRAM is the licensee program that fulfills the requirements of 10 CFR 50.55a(f).

(continue~

1.1-3 Amendment No. 4+&-

SURVEILLANCE REQUIREMENTS continued SR 3.116 SR 3.1.7.7 SR 3.11_7_8 SR 3_ 1_7_9 SR 3.1.7.110 HATCH UNIT 2 SURVElllAN:CE Verify each SILC subsystem manual and power operated valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position_

Verify e.aoh pump develops a flow rate~ 41.2 gpm at.a discharg.e pressure~ 1232 psig_

Verify flow through one SLC subsystem from pump into reactor pressure vessel.

Verify all heat traced piping between storage tan and pump suction is unblocked.

Verify sodium pentaborate enrichment is

~

160.0 atom percent B-10.

3.1-19 SLC System 3.1.7 FREQUENCY l'n accordance with the Surveillance Frequency Control Program rn accordance With the rRsef'u'ice Test.ing Progran1 In accordance with the Surveillance Frequency Control Program l'n accordance with 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 J _ 1_

1~2 Priorto addition to SIL:C tank Amendment No.-21tt

SURVEILLANCE REQUIREMENTS SR 3.4.3.1 HATCH UNIT 2 SURVEILLANCE Verify the safety function lift setpoints of the Sl RVs are as follows:

Number of S/RVs 11 Setpoint

~

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

3 4-6 S/RVs 3.4.3 FREQUENCY Amendment No::-7!49

SURVEILLANCE REQUIREMENTS continued SR 3.5.1.6 SR 3.5.11.7 SR 3.5.1<.8 HATCH UNIT 2 SURVEILlANCE

- - - -NOTE-----------

Only required to be performed prior to entering' MODE 2 from MODE 3 or4, 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 cy cles through one complete cycle of full trav el or is de-energized in the closed position.

Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure.

SYSTEM HEAD CORRESPONDING NO.OF TOAREACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF cs LPCI 2 4250 gpm 1

2 17,000 gpm 2 2113 psig 2

20 psig, 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 pressures 1058 psigi and

~ 920 psig, the HPCI pump can develop a flow rate~ 4250 gpm against a system head corresponding to reactor pressure.

INSERVICE TESTING PROGRAM 3.5-4 ECCS - Operating 3.5.1 FREQUENCY In accordance with the Surveillance Frequency Control Program fn accordance with the IFtservice Testing Program In accordance with the Surveillance Frequency Control Program

{continued)

Amendment No~

SURV EILLANCE REQUIREMENTS continue,

SR 3.5.2.3 SR 3.5.2..4 SR 3.5.2.5 SR 3.5.2.'6 HATCH UNIT 2 SURVEILl!.ANCE Verify, for each required EOCS injection/ spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

NOTE----- -------

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

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

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 PUMPS PRESSURE OF cs LPCI

=: 4250gpm

7700gpm 1

1 2 113 psig,

=:

20psig NOTE------------

Vessel injection/ spray may be excluded!.

Verify each required EGGS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.

ERVICE T~

PROGRA!?1 3. 5~9 EGGS - Shutdown 3.5-2 FREQUENCY In accordance with the Surveillance frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No.....z.-ttr

SURVEIU.ANCE REQUIREME NTS (continued~

SR 3.6.1.3.2 SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.5 HATCH UNIT 2 SURVEILLANCE

- ----------NOTES-----------

1.

2.

Valves and blind flang,es in high radiation areas may be verified by use of administrative means.

Not required to be met for PCIV s that are open under administrative controls.

Verify each primary containment isolation manual valve and blind flang.e that is located outside primary containment and is required to be closed during accident conditions is closed.

*----NOTES-----------

1:.

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

2.

Not required to be met for PCIV s that are open under administrative controls.

Verify each primary containment manual isolation valve and blind flange that is located inside primary containment and is required to be closed during accident conditions is closed.

Verify continuity ofthe traversing in core probe (TIP) shear isolation valve explosive charge.

Verify the isolation time of each power operated and each automatic PCIV, e*xcept for MSl,Vs, is within limits.

~ERVICE TESTING PROGRAM 3.S-11 PCIV s 3.6.1.3 FREQUENCY In accordance with the Surveillance Frequency Control Program Priorto entering MODE 2 or3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 day s In accordance with the Surveillance Frequency Control Program In accordance with the ~n se rv i ce (continued)

Amendment No.--2ttt

SURVEILLANCE REQUIREMENiTS (continued)

SURVEIULANCE SR 3.6.1.3.6 Verify the isolation time of each MSIV is

~ 3 seconds and~ 5 seconds_

l INSERVICE TESTING PROGRAM SR 3.6.1.3.7 Verify each automatic PCIV, excluding EFCVs, actuates to the isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV (of a representative sample) actuates to restrict flow to within limits.

SR 3.6.1.3.9 Remove and test the explosive squib from each shear isolation valve of the TIP system.

SR 3.6.1.3.10 Verify the combined leakage rate for all secondary containment bypass leakage paths is

~ 0.02 La when pressurized to~ Pa.

SR 3.6.1.3.11 Verify combined MSIV leakage rate for all four main steam lines is~ 1'00 scfh when tested at :2:

28.8 psig and < 47.3 psig.

OR Verify combined MSIV leakage rate for all four main steam lines is~ 144 scfh when tested 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 isolation damper to the fully dosed and fully open position_

HATCH UNIT 2 3 6-12 PCIVs 3.6 1.3 FREQUENCY In accordance with the lnseNiee T

n. *---

--** ~

-~ U.111 In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Primary Containment Leakage Rate Testing' Program In accordance with the Primary Containment Leakage Rate Testing Program In accordance with the Surveillance Frequency Control Program Amendment No:-Z-ffi

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.7 ACTIONS continued CONDITION REQUIRED ACTION E.

Required Action and Associated Completion Time not met E.1 Be in MODE 3.

AND E.2 Be in MODE 4.

SURVEILLANCE REQUIREMENTS SR 3.6.1.7.1, SR 3.6.1.7.2 SR 3.6.11.7.3 HATCH UNIT 2

1.

2.

SURVEILLANCE NOTES----------

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

Not required to be met for vacuum brea ers open when performing their intended function.

Verify each vacuum breaker is closed.

Perform a functional test of each vacuum breaker.

Verify the opening setpoint of each vacuum breaker is.s: 0.5 psid.

INSERVICE TESTING PROGRAM 3.6-18 COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the IAservice Testing PFOgr:am l'n accordance with the Surveillance frequency Control Program Amendment No.-2ttT

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS continued SR 3.6.2.3.2 HATCH UNIT 2 SURVEILLANCE Verify each required RIHR pump develops a flow rate ~ noo gpm through the associated heat exchanger while operating in the suppression pool cooling mode.

FREQUENCY In accordance with the lnservice Testin~l PFogram INSERVICE TESTING PROGRAM 3.6-26 Amendment No -t3'5-

5-5 Programs and Manuals (continued) 5-5.5 Component Cyclic or Transient Limit Programs and Manuals 5.5 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'nservice lesting Program is program provides controls for inservice testing of ASME Code Class 1, 2, 3 components includingi applicable supports.

a_

tin9 frequencies specified in Section XI of the ASME Boil Pres re Vessel Code and applicable Addenda are as foll ASME Boi and Pressure Vessel Code a Applicable Addenda Termino y for lnservice Testin Ac

lies Weekly Monthly Quarterly or every 3 month Semiannually or every 6 onths Yearly orannually Require requencies for P, arming In service T tin Activities At least once per 7 days At least once per 31i days At least once per 92 days At least once per 184 days east once per 366 days

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 Program (VFTP)

The VFTP will establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems 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 ventilation zone communicatingi 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. -+74-

1_ 1 Definitions (continued)

E - AVERAGE DISINTEGRATION ENERGY ENGINEERED SAFElY FEATURE (ESF) RESPONSE TIME LEAKAGE INSERVICE TESTING PROGRAM Vogtle Units 1 and 2 Definitions 1_1 E shall be the average (weighted in proportion to the* concentration of each radionuclide in the reactorcoolant at the time of sampling) oHhe 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 noniod'ine activity in the coolant The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its 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 re*sponse 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 measurement, response time may be verified for selected components providedthat the components and the methodology for verification have been previously reviewed and approved by the NRC.

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 specificall)l"locatedl and known either not to interfere-with the operation of leak.age detection systems or not to be pressure boundary LEAKAGE; or

3.

Reactor Coolant System (RCS) LEAKAGE through a steam g:enerator to the Secondary System (primary to secondary LEAKAGE);

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

1.1-3 (continued)

Amendment No. -t¢¢- (Unit 1)

Amendment No. ~

(Unit 2)

SURVEILLANCE REQUIREMENTS SR 3.4.10.1 SURVEILLANCE Verify each pressurizer safety valve is OPERABLE in accordance with the IRseNiee Testing, Program_ Following testing, lift settings shall be within+/- 1%_

Vogtle Units 1 and 2 3.4.10-2 Pressurizer Safety Valves 3.4.10 FREQUENCY Amendment No.-96--(Unit 1)

Amendment No.-'fir(Unit 2)

SURVEIU.ANCE REQUIREMENTS SR 3.4.14.1

1.

SURVEILLANCE

- ----NOTES-----------

Not required to be performed in MODES 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 to s;; 0.5 gpm pernominal inch of valve size up to a maximum of 5 gpm at an RCS pressure

~ 2215 psig and s;; 2255 psig.

RCS PIV Leakage 3.4.14 FREQUENCY In accordance with the LRserviee Tes~i flg Prog1a111, and 18 months Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months (except for valves HV-8701AIB and HV-8702AIB)

AND (continued)

Vogtle Units 1 and 2 3.4.14-3 Amendment No: (Unit 1)

Amendment No.-+4-(Unit 2}

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3_5_2_1 Verify the following. valves are in the listed position with the power lockout switches in the lockout position_

Valve Number Valve Function Valv e Position HV-8835 SI Pump Cold Leg lnj_

OPEN HV-8840 RHR Pump Hot Legi !nj_

CbOSED 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 V erify each ECCS manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position_

SR 3-5.2.3 Verify ECCS piping' is full of water.

SR 3.5.2.4 Verify each ECCS pump's developed head at the test flow point is greater than or equal to the required developed head_

SR 3-5.2.5 Verify each ECCS automatic valv e in the flow path that is not locked, sealed, or otherwise secured in position actuates to the correct position on an actual or simulated actuation signal_

_/

~RVICE TESTING PROGRAM ECCS-Operating 3-5.2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the lnsentice Testing Program 1'

In accordance with the Surveillance Frequency Control Program (continued)

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 SURVEILLANCE REQUIREMENfliS (continued)

SURVEIUANCE SR 3.6.3.4

-NOlES---- -------

SR 3.6.3.5 SR 3.6.3.6 SR 3.6.3.7

1.

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

2.

lhe fuel transfertube blind flange is only required to* be verifiediclosed: once after refuelingi prior to entering MODE 4 from MODES.

Verify each containment isolation manual valve and blind flange that is located inside containment and req,uiredl to be closed during accident conditions is closed, except' forcontainment isolation valves that are open under administrative controls.

Verify the isolation time of each power operated and each automatic containment isolation valve is within limits.

Perform leaka~e rate _t_esting for containment /

purge valves with resilient seals.

7

~

INSERVICE TESTING PROGRAM)

Verify each.automatic containment isolation valve that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

FREQUENCY Prior to enteringi MODE 4 from MODE 5 if not performed within the previous 92 days In accordance with the l'Aserviee TestiAg Prugr=am

/1 In accordance with the Surveillance Frequency Control Program l'n accordance with the Surveillance Frequency Control 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 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:2: 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 :2: 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 IF1seFViee TestiF19 to the required developed head.

~

~::i _,..

1' SR 3.6.6.5 Verify each automatic containment spray valve in n 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.

I 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)

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

Amendment No_...:t4Q... (Unit 2)

ACTIONS (continued)

CONDITl:ONI EL Required Action and B.1'.

ass o ci afe d Campi eti on lime not met AND OR B.2 One or more steam generators (SG) with four or morn MSSVs per SG inoperable.

SURVEILLANCE REQUIREMENJS REQUIRED ACTION Be in MODE 3.

Be in MODE 4.

S URVElllANCE SR 3.7.1.1

NOTE--------

Only required to be performed in MODES 1 and 2.

Verify each required MSSV lift setpoint per Table 3.7.1-2 in accordance with the lnservice

. Following testing, lift settings shall be within+/- 1i%.

MSSVs 3.7.1 COMPLETION TIME

'6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours FREQUENCY In accordance with the l'nservice Testing.

Pm9.ram Vogtle Units 1 and 2

3. 7.1-2 Amendment Ncr.96- (Unit 1)

Amendment No.-14-(Unit 2)

ACTIONS (continued)

CONDmON REQUIRED ACTI:ON:

D.

One or more steam lines D.1 Verify one MSIV sy stem with one MSIV sy stem closed in affected steam inoperable in MODE 2 or line.

3.

E.

One or more steam lines E.1 Verify one MSIV system with two MSl:V systems dosed in affected steam inoperable in MODE 2 or line.

3.

F.

Required Action and f.1, Be in MODE 3.

associated Completion Time of Condition D or AND E not met F.2 Be in MODE 4.

SURVEILl!.ANCE REQUIREMENTS SR 3.7.2.1 SURVEILlANCE

-NOTE------- ----

Only required to be performed in MODES 1 and 2.

V erify closure time of each MSl,V syste m is s 5 seconds on an actual or simulated actuation siQnal.

MSIVs 3.7.2 COMPLETION TIME 7 days AND Once per 7 days thereafter.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Once per 7 days thereafter i6 hours 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months FREQUENCY In accordance with the li 1se1vice Tes tin~

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' C.

One or more MFRV or C.1 Close or isolate bypass MFIV bypass valves valve.

inoperable.

AND C.2 Verify bypass valve is closed or isolated.

0.

Both isolation systems D.1 l:solate affected feedwater inoperable in one or line.

more feedwater lines.

E.

Required Action and E.1 Be in MODEJ_

associated Completion Time not met SURVEILLANCE REQUIREMENTS SR 3.7.3.1 SURVEILLANCE NOTE--------- --

Only required to be performed in MODE 11_

Verify the closure time of each MFIV, MFRV, and associated bypass valve is~ 5 seconds on an actual or simulated actuation signal.

COMPLETION TIME 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Once per 7 days 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

'6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months FREQUENCY l'n accordance with the IRservice Test-iRg Pr=ogr=am INSERVICE TESTING PROGRAM Vogtle Units 1 and 2 3.7.3-2 Amendment No.-9& (Unit 1)

Amendment No. (Unit 2)

SURVEIU.ANCE REQUIREMENTS SURVEILLANCE SR 3.7.9.1 Verify water level of NSCW basin is~ 80.25 ft SR 3.7.9.2 Verify water temperature of NSCW basin is

~ 90°F.

SR 3.7.9.3 Operate each required NSCW cooling tower fan for~ 15 minutes.

SR 3.7.'9.4 Verify NSCW basin transfer pump operation.

~SER~~

PR2_G~

SR 3.7.'9.5 V erify ambient wet-bulb temperature is within the three fan/spray cell region of Figure 3.7.9-1! when one NSCW tower fan/spray cell is out-of-service and daily high temperature (dry-bulb) is forecasted to be > 48"F.

FREQUENCY UHS 3.7.9 In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the lnse!'l'ice Testing PF0~f9:ffi In accordance with the Surveillance Frequency Control Program 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 provides controls forinservice testing of ASME Code Class 1, 2, components_ The program shall include* the following:

a_

Te

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

ASME Boiler and Pre sure Vessel Code and appli le Addenda terminology for inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 year Required Fr

,uencies for performin inservice testin ctivitie*s

east once per 7 days t least once per 31 days At least once per 92 days t least once per 184 days At le t once per276 days At least ce per 366 days 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 _

Vogtle Units 1 and 2 5.5-6

{continued)

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 FNP, HNP, and VEGP Technical Specification Clean Typed Pages

1.1 Definitions ENGINEERED SAFETY FEATURE(ESF)RESPONSE TIME INSERVICE TESTING PROGRAM LEAKAGE Farley Units 1 and 2 Definitions 1.1 The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its 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.

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

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) 1.1-3 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SR 3.4.10.1 SURVEILLANCE Verify each pressurizer safety valve is OPERABLE in accordance with the INSERVICE TESTING PROGRAM. Following testing, lift settings shall be within+/- 1%.

FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Farley Units 1 and 2 3.4.10-2 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.12.1 Verify a maximum of one charging pump is capable of injecting into the RCS when one or more RCS cold legs is s 180°F.

SR 3.4.12.2 Verify a maximum of two charging pumps are capable of injecting into the RCS when all RCS cold legs are > 180°F.

SR 3.4.12.3 Verify each accumulator is isolated.

SR 3.4.12.4 Verify RHR suction isolation valves are open for each required RHR suction relief valve.

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.

SR 3.4.12.6 Verify each required RHR suction relief valve setpoint.

LTOP System 3.4.12 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with 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)

SURVEILLANCE REQUIREMENTS SR 3.5.2.1 SR 3.5.2.2 SR 3.5.2.3 SR 3.5.2.4 SURVEILLANCE

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 with power to the valve operator removed.

Number Position 8884,8886 Closed 8132A, 8132B Open 8889 Closed Function Centrifugal Charging Pump to RCS Hot Leg Centrifugal Charging Pump discharge isolation RHR to RCS Hot Leg Injection Verify each ECCS manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

Verify each ECCS pump's developed head at the test flow point is greater than or equal to the required developed head.

Verify each ECCS automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

ECCS-Operating 3.5.2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.5.2-2 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SR 3.6.3.3 SR 3.6.3.4 SR 3.6.3.5 SR 3.6.3.6 SURVEILLANCE

NOTES--------------------------------

1.

Valves and blind flanges in high radiation areas may be verified by use of administrative 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 blind flange that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

Verify the isolation time of each power operated or automatic containment isolation valve in the INSERVICE TESTING PROGRAM is within limits.

Perform leakage rate testing for containment penetrations containing containment purge valves with resilient seals.

Verify each automatic containment isolation valve that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

FREQUENCY Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program AND Within 92 days after opening the valve In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.6.3-6 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS SR 3.6.6.4 SR 3.6.6.5 SR 3.6.6.6 SR 3.6.6.7 SR 3.6.6.8 SURVEILLANCE Verify each containment spray pump's developed head at the flow test point is greater than or equal to the required developed head.

Verify each automatic containment spray valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

Verify each containment spray pump starts automatically on an actual or simulated actuation signal.

Verify each containment cooling train starts automatically on an actual or simulated actuation signal.

Verify each spray nozzle is unobstructed.

FREQUENCY In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.6.6-3 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

ACTIONS CONDITION REQUIRED ACTION B.

(continued)

B.2

NOTE------------

Only required in MODE 1.

Reduce the Power Range 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.

associated Completion Time not met.

AND OR C.2 Be in MODE 4.

One or more steam generators with 2".: 4 MSSVs inoperable.

SURVEILLANCE REQUIREMENTS SR 3.7.1.1 SURVEILLANCE

N 0 TE----------------------------

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

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

MSSVs 3.7.1 COMPLETION TIME 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 6 hours 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Farley Units 1 and 2 3.7.1-2 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

ACTIONS CONDITION REQUIRED ACTION E.

One or more steam lines E.1 Verify one MSIV closed in with two MSIVs affected steam line.

inoperable in MODE 2 or 3.

F.

Required Action and F.1 Be in MODE 3.

associated Completion Time of Condition D or E AND not met.

F.2 Be in MODE 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE MS IVs 3.7.2 COMPLETION TIME 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Once per 7 days thereafter 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours FREQUENCY SR 3.7.2.1

N 0 TE-------------------------------

0 n I y 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.

Amendment No.

(Unit 1)

(Unit 2)

Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS CONDITION REQUIRED ACTION C.

One or more MFRV C.1 Close or isolate bypass bypass valves valve.

inoperable.

AND C.2 Verify bypass valve is closed or isolated.

D.

Two valves in the same D.1 Isolate affected flow path.

flow path inoperable.

E.

Required Action and E.1 Be in MODE 3.

associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SR 3.7.3.1 SURVEILLANCE Verify the closure time of each Main FW Stop Valve, MFRV, and associated bypass valve is in accordance with the time requirement in the lnservice Testing Plan.

COMPLETION TIME 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Once per. 7 days 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 6 hours FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Farley Units 1 and 2 3.7.3-2 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

SURVEILLANCE REQUIREMENTS SR 3.7.5.2 SR 3.7.5.3 SR 3.7.5.4 SR 3.7.5.5 SURVEILLANCE

N 0 TE---------------------------------

N o t 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 flow test point is greater than or equal to the required developed head.

Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

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 actual or simulated actuation signal.

Verify the turbine driven AFW pump steam admission valves open when air is supplied from their respective air accumulators.

AFW System 3.7.5 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.7.5-3 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

5.5 Programs and Manuals Programs and Manuals 5.5 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 Farley Units 1 and 2 5.5-5 (continued)

Amendment No.

(Unit 1)

(Unit 2)

Definitions 1.1 1.1 Definitions (continued)

END OF CYCLE RECI RC ULA TION PUMP TRIP (EOC-RPT)

SYSTEM RESPONSE TIME INSERVICE TESTING PROGRAM LEAKAGE LINEAR HEAT GENERATION RATE LOGIC SYSTEM FUNCTIONAL TEST HATCH UNIT 1 The EOC-RPT SYSTEM RESPONSE TIME shall be that time interval from initial signal generation by the associated turbine stop valve limit switch or from when the turbine control valve hydraulic control oil pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts of the 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.

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

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

A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all required logic components (i.e., all required relays and contacts, trip 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.

1.1-3 (continued)

Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SR 3.1.7.7 SR 3.1.7.8 SR 3.1.7.9 SR 3.1.7.10 HATCH UNIT 1 SURVEILLANCE Verify each pump develops a flow rate <:: 41.2 gpm at a discharge pressure<:: 1232 psig.

Verify flow through one SLC subsystem from pump into reactor pressure vessel.

Verify all heat traced piping between storage tank and pump suction is unblocked.

Verify sodium pentaborate enrichment is

<:: 60.0 atom percent B-10.

3.1-20 SLC System 3.1.7 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program In accordance with 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 Prior to addition to SLC tank Amendment No.

SURVEILLANCE REQUIREMENTS SR 3.4.3.1 HATCH UNIT 1 SURVEILLANCE Verify the safety function lift setpoints of the S/RVs are as follows:

Number of S/RVs 11 Setpoint

{Qfilg)_

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

3.4-6 S/RVs 3.4.3 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SR 3.5.1.6 SR 3.5.1.7 SR 3.5.1.8 HATCH UNIT 1 SURVEILLANCE

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 cycles through one complete cycle of full travel or is de-energized in the closed position.

Verify the following ECCS pumps develop 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 PUMPS PRESSURE OF cs LPCI

~ 4250 gpm 1

~17, 000gpm 2

~ 113 psig

~ 20 psig

N 0 TE-------------------------------

N o t 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

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

: 4250 gpm against a system head corresponding to reactor pressure.

3.5-4 ECCS - Operating 3.5.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program (continued)

Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SR 3.5.2.3 SR 3.5.2.4 SR 3.5.2.5 SR 3.5.2.6 HATCH UNIT 1 SURVEILLANCE Verify, for each required ECCS injection/ spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

N 0 TE------------------------------

0 n e 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 subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

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

SYSTEM cs LPCI FLOW RATE

~ 4250 gpm

~ 7700 gpm SYSTEM HEAD CORRESPONDING NO. OF TO A REACTOR PUMPS PRESSURE OF 1

~ 113 psig 1

~ 20 psig

N 0 TE--------------------------------

Ve s se I injection/spray may be excluded.

Verify each required ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.

3.5-8 ECCS - Shutdown 3.5.2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SR 3.6.1.3.2 SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.5 HATCH UNIT 1 SURVEILLANCE

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 valve and blind flange that is located outside primary containment and is required to be closed during accident conditions is closed.

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 valve and blind flange that is located inside primary containment and is required to be closed during accident conditions is closed.

Verify continuity of the traversing incore probe (TIP) shear isolation valve explosive charge.

Verify the isolation time of each power operated and each automatic PCIV, except for MSIVs, is within limits.

3.6-11 PC I Vs 3.6.1.3 FREQUENCY In accordance with the Surveillance Frequency Control Program Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM (continued)

Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.6.1.3.6 Verify the isolation time of each MSIV is

~ 3 seconds and :::; 5 seconds.

SR 3.6.1.3.7 Verify each automatic PCIV, excluding EFCVs, actuates to the isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV (of a representative sample) actuates to restrict flow to within limits.

SR 3.6.1.3.9 Remove and test the explosive squib from each shear isolation valve of the TIP system.

SR 3.6.1.3.10 Verify combined MSIV leakage rate for all four main steam lines is :::; 100 scfh when tested at

~ 28.0 psig and < 50.8 psig.

OR 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 to the fully closed and fully open position.

SR 3.6.1.3.13 Verify the combined leakage rate for all secondary containment bypass leakage paths is:::; 0.02 La when pressurized to ~ Pa.

HATCH UNIT 1 3.6-12 PC I Vs 3.6.1.3 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Primary Containment Leakage Rate Testing Program In accordance with the Surveillance Frequency Control Program In accordance with the Primary Containment Leakage Rate Testing Program Amendment No.

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

CONDITION REQUIRED ACTION E.

Required Action and E.1 Be in MODE 3.

Associated Completion Time not met.

AND E.2 Be in MODE 4.

SURVEILLANCE REQUIREMENTS SR 3.6.1.7.1 SR 3.6.1.7.2 SR 3.6.1.7.3 HATCH UNIT 1 SURVEILLANCE

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.

Perform a functional test of each vacuum breaker.

Verify the opening setpoint of each vacuum breaker is ~ 0.5 psid.

3.6-18 COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program Amendment No.

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS (continued)

SR 3.6.2.3.2 HATCH UNIT 1 SURVEILLANCE Verify each required RHR pump develops a flow rate ~ 7700 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.

3.6-26 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Amendment No.

5.5 Programs and Manuals (continued) 5.5.5 Component Cyclic or Transient Limit Programs and Manuals 5.5 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 CORE COOLING SYSTEM (ECCS)

RESPONSE

TIME END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

SYSTEM RESPONSE TIME INSERVICE TESTING PROGRAM ISOLATION SYSTEM RESPONSE TIME LEAKAGE HATCH UNIT 2 The ECCS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS initiation setpoint at the channel sensor until the ECCS 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.

The EOC-RPT SYSTEM RESPONSE TIME shall be that time interval from initial signal generation by the associated turbine stop valve limit switch or from when the turbine control valve hydraulic control oil pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts of the 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.

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

The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation initiation 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 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) 1.1-3 Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SR 3.1.7.6 SR 3.1.7.7 SR 3.1.7.8 SR 3.1.7.9 SR 3.1.7.10 HATCH UNIT 2 SURVEILLANCE Verify each SLC subsystem manual and power operated valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.

Verify each pump develops a flow rate ~ 41.2 gpm at a discharge pressure~ 1232 psig.

Verify flow through one SLC subsystem from pump into reactor pressure vessel.

Verify all heat traced piping between storage tank and pump suction is unblocked.

Verify sodium pentaborate enrichment is

~ 60.0 atom percent B-10.

3.1-19 SLC System 3.1.7 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program In accordance with 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 Prior to addition to SLC tank Amendment No.

SURVEILLANCE REQUIREMENTS SR 3.4.3.1 HATCH UNIT 2 SURVEILLANCE Verify the safety function lift setpoints of the S/RVs are as follows:

Number of S/RVs 11 Setpoint

.{Q§l9l 1150 +/- 34.5 Following testing, lift settings shall be within +/- 1 %.

3.4-6 S/RVs 3.4.3 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SR 3.5.1.6 SR 3.5.1.7 SR 3.5.1.8 HATCH UNIT 2 SURVEILLANCE

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 cycles through one complete cycle of full travel or is de-energized in the closed position.

Verify the following ECCS pumps develop 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 PUMPS PRESSURE OF cs LPCI

4250 gpm 1

17,000 gpm 2

113 psig

20 psig

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

920 psig, the HPCI pump can develop a flow rate ::::: 4250 gpm against a system head corresponding to reactor pressure.

3.5-4 ECCS - Operating 3.5.1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program (continued)

Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SR 3.5.2.3 SR 3.5.2.4 SR 3.5.2.5 SR 3.5.2.6 HATCH UNIT 2 SURVEILLANCE Verify, for each required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

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 subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

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

SYSTEM cs LPCI FLOW RATE

~ 4250 gpm

~ 7700 gpm SYSTEM HEAD CORRESPONDING NO. OF TO A REACTOR PUMPS PRESSURE OF 1

~ 113 psig 1

~ 20 psig

N 0 TE-------------------------------

Ves se I injection/spray may be excluded.

Verify each required ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.

3.5-9 ECCS - Shutdown 3.5.2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SR 3.6.1.3.2 SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.5 HATCH UNIT 2 SURVEILLANCE

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 valve and blind flange that is located outside primary containment and is required to be closed during accident conditions is closed.

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 valve and blind flange that is located inside primary containment and is required to be closed during accident conditions is closed.

Verify continuity of the traversing incore probe (TIP) shear isolation valve explosive charge.

Verify the isolation time of each power operated and each automatic PCIV, except for MSIVs, is within limits.

3.6-11 PC I Vs 3.6.1.3 FREQUENCY In accordance with the Surveillance Frequency Control Program Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM (continued)

Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.6.1.3.6 Verify the isolation time of each MSIV is

~ 3 seconds and :s 5 seconds.

SR 3.6.1.3.7 Verify each automatic PCIV, excluding EFCVs, actuates to the isolation position on an actual or simulated isolation signal.

SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV (of a representative sample) actuates to restrict flow to within limits.

SR 3.6.1.3.9 Remove and test the explosive squib from each shear isolation valve of the TIP system.

SR 3.6.1.3.10 Verify the combined leakage rate for all secondary containment bypass leakage paths is

s 0.02 La when pressurized to ~ Pa.

SR 3.6.1.3.11 Verify combined MSIV leakage rate for all four main steam lines is ::::: 100 scfh when tested at ;::::

28.8 psig and < 47.3 psig.

OR 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 to the fully closed and fully open position.

HATCH UNIT 2 3.6-12 PC I Vs 3.6.1.3 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Primary Containment Leakage Rate Testing Program In accordance with the Primary Containment Leakage Rate Testing Program In accordance with the Surveillance Frequency Control Program Amendment No.

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

CONDITION REQUIRED ACTION E.

Required Action and Associated Completion Time not met.

E.1 AND E.2 Be in MODE 3.

Be in MODE 4.

SURVEILLANCE REQUIREMENTS SR 3.6.1.7.1 SR 3.6.1.7.2 SR 3.6.1.7.3 HATCH UNIT 2 SURVEILLANCE

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.

Perform a functional test of each vacuum breaker.

Verify the opening setpoint of each vacuum breaker is s 0.5 psid.

3.6-18 COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program Amendment No.

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS (continued)

SR 3.6.2.3.2 HATCH UNIT 2 SURVEILLANCE Verify each required RHR pump develops a flow rate ;?: 7700 gpm through the associated heat exchanger while operating in the suppression pool cooling mode.

3.6-26 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Amendment No.

5.5 Programs and Manuals (continued) 5.5.5 Component Cyclic or Transient Limit Programs and Manuals 5.5 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.

1.1 Definitions (continued)

E - AVERAGE DISINTEGRATION ENERGY ENGINEERED SAFETY FEATURE(ESF)RESPONSE TIME INSERVICE TESTING LEAKAGE Vogtle Units 1 and 2 E shall be the average (weighted in proportion to Definitions 1.1 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.

The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its 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.

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

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);

1.1-3 Amendment No.

Amendment No.

(continued)

(Unit 1)

(Unit 2)

SURVEILLANCE REQUIREMENTS SR 3.4.10.1 SURVEILLANCE Verify each pressurizer safety valve is OPERABLE in accordance with the INSERVICE TESTING PROGRAM. Following testing, lift settings shall be within +/- 1 %.

Vogtle Units 1 and 2 3.4.10-2 Pressurizer Safety Valves 3.4.10 FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

SURVEILLANCE REQUIREMENTS SR 3.4.14.1 SURVEILLANCE

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 to ::; 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.

RCS PIV Leakage 3.4.14 FREQUENCY In accordance with the INSERVICE "TESTING 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)

SURVEILLANCE REQUIREMENTS SR 3.5.2.1 Valve Number HV-8835 HV-8840 HV-8813 HV-8806 HV-8802A, B HV-8809A, B SR 3.5.2.2 SR 3.5.2.3 SR 3.5.2.4 SR 3.5.2.5 SURVEILLANCE Verify the following valves are in the listed position with the power lockout switches in the lockout position.

Valve Function SI Pump Cold Leg lnj.

RHR Pump Hot Leg lnj.

SI Pump Mini Flow lsol.

SI Pump Suction from RWST SI Pump Hot Leg lnj.

RHR Pump Cold Leg lnj.

Valve Position OPEN CLOSED OPEN OPEN CLOSED OPEN Verify each ECCS manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

Verify ECCS piping is full of water.

Verify each ECCS pump's developed head at the test flow point is greater than or equal to the required developed head.

Verify each ECCS automatic valve in the flow path that is not locked, sealed, or otherwise secured in position actuates to the correct position on an actual or simulated actuation signal.

ECCS - Operating 3.5.2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program (continued)

Vogtle Units 1 and 2 3.5.2-2 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SR 3.6.3.4 SR 3.6.3.5 SR 3.6.3.6 SR 3.6.3.7 SURVEILLANCE

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 and blind flange that is located inside containment and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

Verify the isolation time of each power operated and each automatic containment isolation valve is within limits.

Perform leakage rate testing for containment purge valves with resilient seals.

Verify each automatic containment isolation valve that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

FREQUENCY Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Vogtle Units 1 and 2 3.6.3-5 Amendment No.

Amendment No.

(Unit 1)

(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.

Amendment No.

(Unit 1)

(Unit 2)

ACTIONS (continued)

CONDITION B.

Required Action and associated Completion Time not met.

One or more steam generators (SG) with four or more MSSVs per SG inoperable.

B.1 B.2 SURVEILLANCE REQUIREMENTS REQUIRED ACTION Be in MODE 3.

Be in MODE 4.

SURVEILLANCE MSSVs 3.7.1 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours FREQUENCY SR 3.7.1.1

N 0 TE------------------------------

Only required to be performed in MODES 1 and 2.

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

Vogtle Units 1 and 2 3.7.1-2 In accordance with the INSERVICE TESTING PROGRAM Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

ACTIONS (continued)

CONDITION REQUIRED ACTION D.

One or more steam lines D.1 Verify one MSIV system with one MSIV system closed in affected steam inoperable in MODE 2 or line.

3.

E.

One or more steam lines E.1 Verify one MSIV system with two MSIV systems closed in affected steam inoperable in MODE 2 or line.

3.

F.

Required Action and F.1 Be in MODE 3.

associated Completion Time of Condition D or AND E not met.

F.2 Be in MODE 4.

SURVEILLANCE REQUIREMENTS SR 3.7.2.1 SURVEILLANCE

N 0 TE-----------------------------

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

Verify closure time of each MSIV system is

~ 5 seconds on an actual or simulated actuation signal.

Vogtle Units 1 and 2 3.7.2-2 MS IVs 3.7.2 COMPLETION TIME 7 days AND Once per 7 days thereafter.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Once per 7 days thereafter 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Amendment No.

(Unit 1)

Amendment No.

(Unit 2)

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

CONDITION REQUIRED ACTION C.

One or more MFRV or C.1 Close or isolate bypass MFIV bypass valves valve.

inoperable.

AND C.2 Verify bypass valve is closed or isolated.

D.

Both isolation systems D.1 Isolate affected feedwater inoperable in one or line.

more feedwater lines.

E.

Required Action and E.1 Be in MODE 3.

associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SR 3.7.3.1 SURVEILLANCE

NOTE-----------------------------

Only required to be performed in MODE 1.

Verify the closure time of each MFIV, MFRV, and associated bypass valve is ~ 5 seconds on an actual or simulated actuation signal.

COMPLETION TIME 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Once per 7 days 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 6 hours FREQUENCY In accordance with the INSERVICE TESTING PROGRAM Vogtle Units 1 and 2 3.7.3-2 Amendment No.

~ (Unit 1)

Amendment No.

(Unit 2)

SURVEILLANCE REQUIREMENTS SR 3.7.9.1 SR 3.7.9.2 SR 3.7.9.3 SR 3.7.9.4 SR 3.7.9.5 SURVEILLANCE Verify water level of NSCW basin is ~ 80.25 ft.

Verify water temperature of NSCW basin is

90°F.

Operate each required NSCW cooling tower fan for ~ 15 minutes.

Verify NSCW basin transfer pump operation.

Verify ambient wet-bulb temperature is within the three fan/spray cell region of Figure 3.7.9-1 when one NSCW tower fan/spray cell is out-of-service and daily high temperature (dry-bulb) is forecasted to be> 48°F.

FREQUENCY UHS 3.7.9 In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the INSERVICE TESTING PROGRAM In accordance with the Surveillance Frequency Control Program Vogtle Units 1 and 2 3.7.9-3 Amendment No.

Amendment No.

(Unit 1)

(Unit 2)

5.5 Programs and Manuals 5.5.8 Not Used.

Vogtle Units 1 and 2 5.5-6 Programs and Manuals 5.5 (continued)

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 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 BASES SR 3.0.2 and SR 3.0.3 apply in Chapter 5 only when invoked by a Chapter

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

SRs SR 3.0.1 Farley Units 1 and 2 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 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)

B3.0-13 Revision 35 I

BASES SR 3.0.1 (continued)

SR 3.0.2 When a Section 5.5, "Programs and Manuals,"

specification states that the provisions of SR 3.0.2 are applicable, a 25%

extension of the testing interval, whether stated in the specification or incorporated by reference, is permitted.

SR Applicability B 3.0 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 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 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).

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

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

BASES SR 3.0.2 (continued)

SR 3.0.3 When a Section 5.5, "Programs and Manuals,"

specification states that the provisions of SR 3.0.3 are applicable, it permits the flexibility to defer declaring the testing requirement not met in accordance with SR 3.0.3 when the testing has not been completed within the testing interval (including the allowance of SR 3.0.2 if invoked by the Section 5.5 specification).

Farley Units 1 and 2 SR Applicability B 3.0 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 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 performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.

This delay period provides adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.

The basis for this delay period includes consideration of unit conditions, 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)

B 3.0-15 Revision 35

BASES SURVEILLANCE REQUIREMENTS Farley Units 1 and 2 SR 3.4.12.1. SR 3.4.12.2. and SR 3.4.12.3 (continued)

LTOP System B 3.4.12 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 I 11se1"11ice Testi119 P1091a111 which is based on the requirements of the ASME OM Code (Ref. 7)~

INSERVICE TESTING PROGRAM (continued)

B 3.4.12-11 Revision

BASES SURVEILLANCE REQUIREMENTS REFERENCES Farley Units 1 and 2 LTOP System B 3.4.12 SR 3.4.12.6 (continued)

INSERVICE TESTING PROGRAM The RHR relief valve setpoints are verified in accordance with the I Surveillance Frequency Control Program. Per the ln~el"Oiee Te~ting 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.

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).

B 3.4.12-12 Revision

BASES SURVEILLANCE REQUIREMENTS INSERVICE TESTING PROGRAM Farley Units 1 and 2 SR 3.4.14.1 (continued)

RCS PIV Leakage B 3.4.14 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, 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)

B 3.4.14-6 Revision

BASES SURVEILLANCE REQUIREMENTS Farley Units 1 and 2 SR 3.5.2.2 (continued)

ECCS - Operating B 3.5.2 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.

B 3.5.2-9 Revision

BASES SURVEILLANCE REQUIREMENTS (continued)

Farley Units 1 and 2 SR 3.6.3.3 Containment Isolation Valves B 3.6.3 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 reevaluation of STI Evaluation Number 558904 in accordance with the Surveillance Frequency Control Program.

INSERVICE TESTING PROGRAM (continued)

B 3.6.3-12 Revision

BASES SURVEILLANCE REQUIREMENTS SR 3.6.6.2 (continued)

Containment Spray and Cooling Systems B 3.6.6 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

BASES APPLICABLE SAFETY ANALYSES (continued)

LCO MSSVs B 3.7.1 MSSVs on the same steam generator it is necessary to prevent this power increase by lowering the Power Range Neutron Flux-High 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).

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

BASES ACTIONS SURVEILLANCE REQUIREMENTS Farley Units 1 and 2 B.1 and B.2 (continued)

MSSVs B 3.7.1 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.

SR 3.7.1.1 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)

B 3.7.1-6 Revision I

BASES SURVEILLANCE REQUIREMENTS REFERENCES Farley Units 1 and 2 SR 3.7.2.1 (continued)

MS I Vs B 3.7.2 INSERVICE TESTING PROGRAM 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.

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).

B 3.7.2-7 Revision

BASES ACTIONS SURVEILLANCE REQUIREMENTS REFERENCES Farley Units 1 and 2 Main FW Stop Valves and MFRVs and Associated Bypass Valves B 3.7.3 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.

SR 3.7.3.1 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

1. FSAR, Section 10.4.7.

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

B 3.7.3-6 Revision

BASES SURVEILLANCE REQUIREMENTS REFERENCES Farley Units 1 and 2 Containment Penetrations B 3.9.3 INSERVICE TESTING PROGRAM SR 3.9.3.2 (continued)

\\

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.

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.

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 HATCH UNIT 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)

B 3.0-12 REVISION 52

BASES SR 3.0.1 (continued)

SR 3.0.2 When a Section 5.5, "Programs and Manuals,"

specification states that the provisions of SR 3.0.2 are applicable, a 25%

extension of the testing interval, whether stated in the specification or incorporated by reference, is permitted.

SR Applicability B 3.0 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.

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 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).

.---------7-"'

The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency.

This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs. The exceptions to SR 3.0.2 are those Surveillances for which the 25% extension of the interval specified in the Frequency does not apply. These exceptions are stated in the individual Specifications. The requirements of regulations take (continued)

B 3.0-13 REVISION 52

BASES SR 3.0.2

~~~~~(-co_n_t_in_u~ed)

~

Examples of where SR I/

3.0.2 does not apply are in the Primary 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 1 O 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.

SR 3.0.3 When a Section 5.5, "Programs and Manuals,"

specification states that the provisions of SR 3.0.3 are applicable, it permits the flexibility to defer declaring the testing requirement not met in accordance with SR 3.0.3 when the testing has not been completed within the testing interval (including the allowance of SR 3.0.2 if invoked by the Section 5.5 specification).

HATCH UNIT 1 SR Applicability B 3.0 precedence over the TS. Therefo1 e, vol 1e11 a test i11te1 val is specified 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 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 Lealcage Rete Testing Progra111, "SR 3.0.2 is riot applicable." Tl1is exception is provided eeeause tl9e pregraffi already includes exte11sior 1 of test intervals. 1 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 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 performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.

This delay period provides adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.

The basis for this delay period includes consideration of unit conditions, 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 (continued)

B 3.0-14 REVISION 52

BASES SURVEILLANCE REQUIREMENTS (continued)

INSERVICE TESTING PROGRAM HATCH UNIT 1 SR 3.1.7-5 SLC Sy stem B 3.1-7 This Surveillance* requires an examination of the sodium pentaborate solution by using chemical 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 and 3.1. 7-2). SR 3.1.7.5 must be performed

.any time sodium pentaborate or water is added to the storage tank solution to determine that the* boron solution concentration is within the specified 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 Surveillance frequency is controlled under the Surveillance Frequency Control Program_

SR 3.1.7.7 Demonstrating that each SlC System pump develops a flow rate ~ 41.2 gpm at a discharge pressure ~ 1232 psig ensures that pump performance has not degraded during the fuel cyole. This minimum pump flow rate requirement ensures that, when combined with the sodium pentaborate solution concentration requirements, the rate of neg:ative reactivity insertion from the SLC System will adequately compensate forthe positive reactivity effects encountered during power reduction, cooloown of the moderator, and xenon decay_

Additionally, the minimum pump flow rate requirement ensures that adequate buffering agent will reach the suppression pool to maintain pH at or above 7.0 post-ILOCA_ This test confirms one point on the pump design curve and is indicative of overall performance. Such in service inspections confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance*. The frequency of this Surveillance is in accordance with the l'nserviee Testing PfOgrsm.

These Surveillances ensure that there is a functioning flow path from the sodium pentaborate solution storage tank to the RPV, including, the firing of an explosive valve. The replacement charge for the explosiv e valve shall-be from the same manufactured batch as the one fired or from 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 verifying flow from the pump to the RPV is to pump demineralized water from a te*st tank (continued)

B 3_ 1-40 REVISION

BASES (continued)

ACTIONS SURVEILLANCE REQUIREMENTS INSERVICE TESTING PROGRAM ____,

REFERENCES HATCH ur~IT 1 A.1' and A.2 S/RVs B 3.4.3 With 1 SRN inoperable, no action is required, because an analysis demonstrated that the* remaining 10 SRNs are capable of providing the necessary overpressure protection. (See Ref. 5.)

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

violation of the ASME Code limit on reactor pressure. The plant must be brnughH o*a MOOE in which the LCO does not apply. To achieve this status, the plant must be brought to M.ODE 3 within 112 hours0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months and

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

SR 3.4.3.1 This Surveillance requires that the S/RVs will open at the pressures assumed in the safety analysis of Reference 1. The demonstration 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 pressure shall correspond to ambient cond'itions ofthe valves at nominal operating temperatures and pressures. The S/RV setpoint is +/- 3% for OPERABILITY; however, the valves 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.

1.

FSAR, Appendix M.

2.

FSAR, Section 14.3.

3.

INRC No.93-102, "Final Policy Statement on Technical Specification rmprovements," July 23, 19,93_

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

B 3.4-12 REVISION._

BASES SURVEILLANCE REQUIREMENTS INSERVICE TESTING PROGRAM HATCH UNIT 1 SR 3.5.1'.6 (continued)

ECCS - Operating 8 3.5.1 The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. Howev er, this SR is modified by a Note that states the Surveillance is only required to be performed priorto entering MODE 2 from MODE 3 or4, when in MODE 4> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Verification during orfollowingMODE 4> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and priorto enterin9 MODE 2 from MODE 3 or4 is an exception to the normal g,eneric valv e cyclin9 Frequency of 92 days, but is considered acceptable due to the demonstrated reliability ofthese valves. The 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is intended to indicate an outage of sufficient duration to allow for scheduling: and proper performance of the Surveillance. If the valv e is inoperable and in the open position, the associated LPCI subsystem must be declared inoperable.

SR 3.5.1.7. SR 3.5.1.8. and SR 3.5.1.9 The performance requirements of the low pressure ECCS pumps are determined through application of the 10 CfR 50, Appendix K criteria (Ref. 7}. This periodic Surveillance is performed (in accordance with the ASME OM Code* requirements for the ECCS pumps) to v erify that the ECCS pumps will develop the flow rates required by the respectiv e analyses. The low pressure ECCS pump flow rates ensure that adequate core cooling is provided to satisfy the acceptance criteria of Reference '9. The pump flow rates are v erified against a system head equiv alent to the RPV pressure expected durin9 a L:OCA. The total system pump out.let. pressure is adequate to ov ercom e the elevation head pressure between the pump suction and the v esse'l discharg.e, the pi pin gr friction losses, and RPV pressure present during a lOCA. These values may be established during preoperational testing~

The flow tests fort.he HPCI Sy stem are performed at two different pressure ranges such that sy stem capability to provide* rated fl ow is tested at both the hi.gher and lower operatin9 ran9es of the system.

The pump flO\\N rates are v erified against a sy stem head corre*spondngto the* RPV pressure. The total' system pump out.let pressure is adequate to overcome the elevation head pressure between the pump suction and the vessel discharge., the piping!

friction losses, and RPV pressure. Addlionally, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue* to control reactor pressure when the HPGI Sy stem div erts steam flow. The reactor steam pressure must be~ 920 psigto perform SR 3.5.1.8 and~ 150 psig to perform SR 3.5.1!.9. Adequate (continued)

B 3.5-10 REVISION _

BASES StJRVEILLANCE REQUIREMENTS INSERVICE TESTING PROGRAM HATCH UNIT 1 ECCS - Operating B 3.5. 1 SR 35. 1. 7. SR 3.5. 1.8. and SIR 3.5. 1.9 (continued) steam flow for SR 3-5. 1.8 is represented by at least two turbine bypass valves open, or ~ 200 MWE from the main turbine generator; and for SR 3.5. 11_9 adequate steam flow is represented by at least 1.25 turbine bypass valv es open, or total steam flow ~ 1 E6 lb/hour.

Therefore, sufficient time is allowed after adequate pressure and flow are achieved! to perform these tests. Reactor startup is allowed prior to performing. 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 believe that IHPCI is inoperable_ Therefore, 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 after the 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 sufficient to achieve stable conditions for testing and provides a reasonable time to complete i.he SR The Frequency for SR 3.5. 1i_ 7 is consistent with the IRservice TesliRg Progl'3m pump testing requirements_ The Surveillance Frequency is controlled under the Surveillance Frequency Control Program_

SR 3.5.1.10 The ECCS subsystems are required to actuate automatically to perform their design functions. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of HPCI, GS, and LPCI will cause the systems or subsystems to operate as designed, including actuation of the system throughout its emergency operating sequence, automatic pump startup and actuation of all automatic valves to their required positions_ This SR also ensures that the HPCI System will automatically restart on an RPV low water level (Level 2) signal received subsequent to an RPV high water level (Lev el 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5. 1 overlaps this Surveillance to provide complete testing of the assumed safety function_

(continued}

B 35-11 REVISION _

BASES SURVEILLANCE REQUIREMENTS INSERVICE TESTING PROGRAM HATCH UNIT 1 SR 3.6.1.3.5 (continued)

PCIVs 8 3.6.1.3 closure isolation time* is demonstrated by SR 3.6.1.3.6. The isolation time 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 valve 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 SR is in accordance with the requirements of the IAservice Testifl§ Pro§Jam.

SR 3.6.1 -3.6 Verifyin9that the isolation time of each MSIV is within the specified limits is required to demonstrate OPERABILITY. The isolation time test ensures that the MSIV will isolate in a time period that does not exceed the times assumed in the OBA analyses. This ensures that the calculated radiological consequences ofthese events remain within 1~ 0 CFR 50.67 limits. The Frequency of this SR is in accordance with the requirements of the 1Rsel"l1iee TestiRg Program.

SR 3.6.1.3.7 Automatic PClVs dose on a primary containment isolation signal to prevent leakag.e of radioactiv e material from primary containment following a OBA. This SR ensures that each automatic PCIV will 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 complete testing of the safety function.

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

SR 3.6.1.3.8 This SR requires a demonstration that eaoh reactor instrumentation line excess flow check valve (EFCV) (of a representative sample) is OPERABLE by verifyingi that the valv e reduces flow to within limits on an actual or simulated instrument line break condition. (The representative sample consists of an approximately equal number of EfCVs, such that each EFCV is tested. In addition, the EFCVs (continued)

B 3. 6~24 REVISION _

BASES SURVEILLANCE REQUIREMENTS INSERVICE TESTING PROGRAM HATCH UNIT 1 Reactor Building-to-Suppression ChamberVacuum Breakers B 3.6.1.7 SR 3.6.1. 7.1 (continued~

Two Notes are added to this SR The first Note allows reactor buildingi-to-suppression chamber vacuum breakers opened in conjunction with the performance of a Surveillance to not be considered as failing this SR. These periods of opening vacuum breakers are controlled by plant procedures and do not represent inoperable vacuum breakers. The second Note is included to clarify that vacuum breakers, which are open due to an actual differential pressure, are not considered as failing this SR.

SR 3.6.1.7.2 Each vacuum breaker must be cycled to ensure that it opens properly to perform its design function and returns to its fully closed position.

This ensures that the safety analy sis assumptions are valid. The 92 day Frequency of this SR is in accordance with the requirements of the IRserviee TesliRg, Prngf8:ffi.

Demonstration of vacuum breaker opening setpoint is necessary to ensure that the safety analysis assumption regarding vacuum breaker full open differential pressure of~ Oi.5 psid is valid. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

B 3.6-39 REVISION

BASES SURV51LLANCE REQUIREMENTS (continued)

INSERVICE TESTING PROGRAM REFERENCES HATCHUNIT1 SR 3.6.2.3.2 RHR Suppression Pool Cooling B 3.6.2.3 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 ASME OM Code* (Ref. 2). This test confirms,one point,on the* pump design curve, andthe results are* indicative *Of overall performance. Such ins e rvi ce* tests confirm oo mp on ent OPERABILITY and detect in ci pie nt failures by indicating abnormal performance. The Frequencyofthis SR is in accordance with the lnservice Testin§ Prn§raffi.

1.

FSAR, Sections 5.2and14.4.3.

2.

ASME Code for Operation and Maintenance of Nuclear Power Plants.

3.

NRC No.93-102, "1Final Policy Statement on Technical Specification Improvements," July23, 199'3.

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

iinvoked by a Chapter 5 Specification.

SR 3.0.1 HATCH UNIT 2 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)

B 3.0-12 REVISION 58

BASES SR 3.0.1 (continued)

SR 3.0.2 When a Section 5.5, "Programs and Manuals,"

specification states that the provisions of SR 3.0.2 are applicable, a 25%

extension of the testing interval, whether stated in the specification or incorporated by reference, is permitted.

HATCH UNIT 2 SR Applicability B 3.0 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.

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 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).

The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency.

This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs. The exceptions to SR 3.0.2 are those Surveillances for which the 25% extension of the interval specified in the Frequency does not apply. These exceptions are stated in the individual Specifications. The requirements of regulations take continued B 3.0-13 REVISION 58

BASES SR 3.0.2 (continued)

~

Examples of where SR _/

3.0.2 does not apply are in the Primary 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.

SR 3.0.3 When a Section 5.5, "Programs and Manuals,"

specification states that the provisions of SR 3.0.3 are applicable, it permits the flexibility to defer declaring the testing requirement not met in accordance with SR 3.0.3 when the testing has not been completed within the testing interval (including the allowance of SR 3.0.2 if invoked by the Section 5.5 specification).

HATCH UNIT 2 SR Applicability B 3.0 precedence over the TS. Tl 1erefo1 e, vvl 1e11 a test i11te1 val is specified 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 applioable." An example of an mmeption when the test ir1teF11al is specified in ti 1e regulatio11s is ti 1e t<.lote ii r ti re Pli111a1 y Co11tai11111e11t Lealcage Rate Testir1g Prograni, "SR 3.0.2 is 11ot applicable." Tl1is exception is provided because the prograffi already includes exte11sio11 of test i11tervals.1 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 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 performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.

This delay period provides adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.

The basis for this delay period includes consideration of unit conditions, 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 (continued)

B 3.0-14 REVISION 58

BASES SURVEILLANCE REQUIREMENTS INSERVICE TESTING PROGRAM HATCH UNIT 2 SR 3.1. 7.5 (continued)

SLC System B 3.1.7 concentration of boron exists in the storage tank (within Region A limits of Figures 3.1.7-1, and 3.1.7-2). SR 3.1.7.5 must be performed anytime sodium pentaborate or water is added to the storage tank solution to determine that the boron solution concentration is within the specified 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 precipitation occurred. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.1.7.7 Demonstrating that each SLC System pump develops a flow rate~ 41.2 gpm at a discharge pressure~ 1232 psig ensures that pump performance has not degraded during; the fuel cycle. This minimum pump flow rate requirement ensures that, when combined with the sodium pentaborate solution concentration requirements, the rate of negative reactivity insertion from the SILC System will adequately compensate for the positive reactivity effects encountered during power reduction, cool down of the moderator, and xenon decay.

Additionally, the minimum pump flow rate requirement ensures that adequate buffering agent will reach the suppression 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 overall performance. Such in service inspections confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. The Frequency of this Surveillance is in accordance with the IRseFViee TestiRQ ProgffHft.

These Surveillances ensure that there is a functioning fl O\\!V path from the sodium pentaborate solution storage tank to the RPV, including the firing of an explosive valve. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch that has been certified by having one of that batch successfully fired. The Surveillance may be performed in separate steps to prevent injecting* boron into the RPV. An acceptable method for verifying, fl ow from the pump to the RPV is to pump de mineralized water from a test tank through one (continued)

B 3.140 REVISION

BASES APPUCABllllY (continued)

ACTIONS SURVEILLANCE REQUIREMENTS S/RVs B 3.4.3 from the core until such time that the Residual Heat Removal (RHR)

System is capable of dissipatingthe oore heat.

In MODE 4, decay heat is low enougrldto ambient conditions of the valves at norrinal operating temperatures and pressures. The S/RV setpoint is+/- 3% forOPERABllU1Y; however, INSERVICE the valves are resetto +/- 11% duringithe Surveillance to allow for drift TESTING PROGRAM The Frequency ofthis SR is in accordance with the fnserviee Testin~

~--~

Pr-o~Fa: FR.

(continued)

HATCH UNIT 2 B 14-12 REVISION _

BASES SURVEILLANCE IREQUfREMENfTS INSERVICE TESTING PROGRAM HATCH UNIT 2 SR 3.5_ 1.6 (continued)

ECCS-Operating B 3.5.1 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 MODE 4> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Verification during or follCJ1111ing MODE 4 > 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and prior to entering MODE 2 from MODE 3 or 4 is an exception to the normal l'Rsep,iice TestiA§ PFO§Faffl g;eneric valve cycling Frequency but is considered acceptable due to the demonstrated reliabil~y of these valves. 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 and proper performance of the Surveillance. If t.he valv e is inoperable and in the open posit.ion, t.he associatedlPCll subsystem must be declared inoperable.

SR 3.5.1.7. SR 3.5.1.8. and SR 3.5.1.9 The performance requirements of the low pressure ECCS pumps are determined through application of the 10CFR 50, Appendix K criteria (Ref. 8). This periodic Surveillance is performed (in accordance with the ASME OM Code requirements for the ECCS pumps) to verify that the ECCS pumps will develop the flow rates required by the respective analyses. The low pressure ECCS pump flow rates ensure that adequate core cooling is provided to satisfythe acceptance criteria of Reference 10. The pump flow rates are verified against a system head equivalent to the RPV pressure expected during a lOCA. The total system pump outlet pressure is adequate to overcome the elevation head pressure between the pump suction and the vessel discharge, the piping friction losses, andRPV pressure present during a LOCA. These values may be established during preoperational testingL The flow tests for the IHPCI Sy stem are performed at two different pressure ranges such that sy stem capability to provide rated flow is tested at both the higher and lower operating ranges of the system.

The pump flow rates are verified against a system head corresponding to the RPV pressure. The total system pump outlet pressure is adequate to overcome the elevation head pressure between the pump suction and the vessel discharge, the piping friction losses, and IRPV pressure. Addtionally, adequate steam flow must be passingthrough the main turbine orturbine bypass valves to continue to control reactor pressure when the HPC! System diverts 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)

B 3.5-10 REVI S I ON ~

BASES SURVEILLANCE REQUIREMENTS INSERVICE TESTING PROGRAM HATCH UNIT 2 ECCS - Operating B 3.5.1 SR 3_5_ 1_ 7. SR 3_5_ 11_8, and SR 3-5.1.9 (continued) steam flow for SR 3_5_ 11.8 is represented by at least two turbine bypass valves open, or~ 20Qi MWE from the main turbine-generator, and for SR 3.5.1.9 adequate steam flow is represented by at least 125 turbine bypass valves open, or total steam flow~ 1E6 lb/hour_

Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform these tests. Reactor startup is allowed prior to performing 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 believe 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 provides 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 requirements. The Frequencies for SR 3.5.1.8 and SR 3.5.1 _'9 are based on operating experience, equipment reliability, and plant risk, and are controlled under the Surveillance Frequency Control Program_

SR 3.5.1.10 The ECCS subsystems are required to actuate automatically to perform their design functions. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of HPCI, CS, and LPCI will cause the systems or subsystems to operate as designed, including actuation of the system throughout its emerg,ency operating sequence, automatic pump startup and actuation of all automatic valves to their required positions. This SR also ensures that the HPCI: System will automatically restart on an RPV low water level (Level 2) signal received subsequent to an RPV high water level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The L:OGl.C SYSTEM FUNCTIONAL TEST performed in lCO 3.3-5. 1 overlaps this Surveillance to provide complete testing of the assumed safety function.

(continued)

B 3.5-11 REVISION

BASES SURVElt!J\\NCE REQUIREMENTS INSERVICE TESTING PROGRAM HATCH UNIT 2 SR 3.6.1!.3.5 (continued}

PCIV s B 3.6.1.3 closure isolation time is demonstrated by SR 3.6.1.3.6. The isolation time test ensures that each valve will isolate in a time period less than or equal to that listed in the FSAR and that no degradation affecting, valv e closure since the performance of the last surveillance has oocurred. (EFCVs are not required to be tested because they hav e no specified time limit). The* Frequency of this SR is in accordance with the requirements of the l'IT':'l"T'!Trr-P--t-i:ir<:t-rnrr""P"rnrnr::rnr-SR 3.6.1.3.6 Verifying that the isolation time of each MSIV is within the specified limits is required to demonstrate OPERABILITY. The isolation time test ensures that the MSIV will isolate in a time period that does not exceed the times assumed in the OBA analyses. This ensures that the calculated radiological consequences of these ev ents remain within 1,0 CFR 50.167 limits. The Frequency of this SR is in accordance with the requirements of the l ~eTY-1

e.-il-eST+.R&+'f&e-~R

-
SR 3.6.1.3. 7 Automatic PCIV s close on a primary containment isolation signal to prevent leakage of radioactiv e material from primary containment following a DBA. This SR ensures that each automatic PCIV will actuate to its isolation position on a primary containment isolation signal. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.1i.6 overlaps this SR to provide complete testing 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 alve (EFCV) (of a representative sample) is OPERABLE by verifying that the valve reduces flow to within limits on an actual or simulated instrument line break condition. (The representativ e sample consists of an approximately equal number of EFCVs, such that each EFCV is tested at least once every 10 years
[nominal]. In addition, the EFCVs in the sample are representative of the various plant configurations, models, sizes, and operating environments. This ensures that any potentially common problem (continued)
B 3.6--24 REVISION
BASES SURVEILl..ANCE REQUIREMENTS INSERVICE TESTING PROGRAM REFERENCES HATCH UNIT 2 Reactor Building-to-Suppression Chamber Vacuum Breakers B 3_6_1_7 SR 3_'6_ 1_ 7_ 1 (continued)
Two Notes are added to this SR The first N'ote allows reactor building-to-suppression chamber vacuum breakers opened in conjunction with the performance of a Surveillance to not be c onsidered as failing this SR These periods of opening vacuum ~
breakers are controlled by plant procedures and do not represent inoperable* vacuum breakers. The second N'ote is included to clarify that vacuum breakers, which are* open due to an actual differential pressure, are* not considered as failing this SR SR J _.S_ 1I2 Each vacuum breaker must be cycled to ensure that it opens properly to perform its design function and returns to its fully closed position_
This ensures that the safety analy sis assumptions are valid. The 92 day Frequency of this SR is in accordance with the requirements of the l'nSierviee Testing Program.
Demonstration of vacuum breaker opening1 setpoint is necessary to ensure that the safety analysis assumption reg:arding vacuum breaker full open differential pressure of::::; 0.5 psid is valid. The Surveillance Frequency is controlled underthe Surveillance Frequency Control Program.
1_
FSAR, Section 6.2.1_
2.
NRC No. '9J-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.
B 3_&-41 REVISlON
BASES SURVEILLANCE REQUIREMENTS
{continued)
INSERVICE TESTING PROGRAM REFERENCES HATCHUNIT2 SR 3.6.2.3.2 RHR Suppression Pool Cooling B 3.6.2.3 Verifying1that each required RHR pump develops a flow rate
~ 7700 gpmwhile*operating in the suppression pool oooling; mode with flow th rough 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 ASME OM Code (Ref. 2). This test oonfirms one point on the pump design curve, and the res u Its a rein di cative of ove ra II pe rfo rrnan ce*. Su ch ins e rvi ce tests confirm.componentOPERABILITY and detect incipient fa ilures by indicating1 abnormal performance. The Frequency of this SR is in accordance with the* lr1se1 virnTesti11g Program
1.
FSAR, Section 62.2.
2.
ASME Code for Operation andMaintenance*of Nuclear Power Plants (OM Code)
3.
NR:C No. '93-102, "'Final Policy Statement on Technical Specification Improvements," July 23, 1993.
B 3.6-59 REVISION
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====lSpecification.
SRs SR 3.0.1 Vogtle Units 1 and 2
'---'-~~~~~~~~~~~~~~----'
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 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 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 (continued)
B 3.0-13 Rev. 3 - 9/06
BASES SR 3.0.1 (continued)
SR 3.0.2 When a Section 5.5, "Programs and Manuals,"
specification states that the provisions of SR 3.0.2 are applicable, a 25%
extension of the testing interval, whether stated in the specification or incorporated by reference, is permitted.
SR Applicability B 3.0 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 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).
The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency.
This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs. The exceptions to SR 3.0.2 are those Surveillances for which the 25% extension of the interval specified in the Frequency does not apply. These exceptions are stated in the individual Specifications. The re recedence over the TS. Therefore, vvnen a test interval is speoified in tne Fegulations, tne test interval eannot SR 3.0.2 be extended by the T-S, a11d ti 1e SR i11cludes a Note i11 ti 1e F1 eque1 icy statiJ 19 ti 1at "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
BASES SR 3.0.2 (continued)
SR 3.0.3 When a Section 5.5, "Programs and Manuals," specification states that the provisions of SR 3.0.3 are applicable, it permits the flexibility to defer declaring the testing requirement not met in accordance with SR 3.0.3 when the testing has not been completed within the testing interval (including the allowance of SR 3.0.2 if invoked by the Section 5.5 specification).
Vogtle Units 1 and 2 SR Applicability B 3.0 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 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 performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.
This delay period provides adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.
The basis for this delay period includes consideration of unit conditions, 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.
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) 83.0-15 Rev. 4-9/06
BASES (continued)
ACTIONS SURVEILLANCE REQUIREMENTS Vogtle Units 1 and 2 Pressurizer Safety Valves B 3.4.10 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.
SR 3.4.10.1 INSERVICE TESTING PROGRAM
~
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)
B 3.4.10-4 Rev.
BASES (continued)
SURVEILLANCE REQUIREMENTS Vogtle Units 1 and 2 SR 3.4.12.1 and SR 3.4.12.2 COPS B 3.4.12 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 Frequency Control Program.
INSERVICE TESTING PROGRAM SR 3.4.12.3 I
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)
B 3.4.12-12 REVISION
BASES ACTIONS SURVEILLANCE REQUIREMENTS Vogtle Units 1 and 2 C.1 (continued)
RCS PIV Leakage B 3.4.14 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.
SR 3.4.14.1 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 TestiA§ 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)
B 3.4.14-5 Revision No.
BASES SURVEILLANCE REQUIREMENTS Vogtle Units 1 and 2 SR 3.5.2.2 (continued)
ECCS -
Operating 8 3.5.2 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.
SR 3.5.2.4 lnservice 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.
8 3.5.2-9 Rev.
BASES SURVEILLANCE REQUIREMENTS Vogtle Units 1 and 2 SR 3.6.3.4 (continued)
Containment Isolation Valves B 3.6.3 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)
B 3.6.3-11 REVISION
BASES SURVEILLANCE REQUIREMENTS (continued)
Vogtle Units 1 and 2 SR 3.6.6.3 Containment Spray and Cooling Systems B 3.6.6 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!§IFBITl,
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)
B 3.6.6-8 REVISION
BASES LCO (continued)
APPLICABILITY ACTIONS Vogtle Units 1 and 2 MSSVs B 3.7.1 on allowable THERMAL POWER (to meet ASME Code requirements 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.
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.
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)
B 3.7.1-3 Revision No.
BASES ACTIONS SURVEILLANCE REQUIREMENTS A.1 and A.2 (continued)
MSSVs B 3.7.1 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.
SR 3.7.1.1 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.
BASES SURVEILLANCE REQUIREMENTS REFERENCES Vogtle Units 1 and 2 SR 3.7.2.1 (continued)
MS IVs 8 3.7.2 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.
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).
8 3.7.2-7 Revision No.
BASES ACTIONS SURVEILLANCE REQUIREMENTS D.1 (continued)
MFIVs and MFRVs and Associated Bypass Valves B 3.7.3 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 isolated 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.
SR 3.7.3.1 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 closure times are assumed in the accident and containment analyses. This Surveillance is normally performed upon returning the unit to operation following a refueling outage.
This surveillance is modified by a Note that allows entry into and operation in MODE 2 prior to performing the SR.
The Frequency for this SR is in accordance with the 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.
BASES (continued)
SURVEILLANCE REQUIREMENTS SR 3.7.5.1 AFW System B 3.7.5 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
BASES SURVEILLANCE REQUIREMENTS REFERENCES Vogtle Units 1 and 2 SR 3.7.9.3 (continued)
UHS B 3.7.9 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.
/
SR 3.7.9.5 INSERVICE TESTING PROGRAM 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.
1.
FSAR, Subsection 9.2.5.
2.
Regulatory Guide 1.27.
3.
ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code).
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 Description and Assessment of the Proposed Alternative to the ASME Code 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 1 O 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 1 O CFR 50.55a(f) requirements as allowed by 1 O 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 1 O 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 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 through 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 1 O CFR 50.55a(z)(2), and proposes an alternative to the requirements of 1 O 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 1 O 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 1 O CFR 50.55a(z)(2), in that the existing E5-2 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 1 O 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 Inservice Testing Program Removal & Clarify SR Usage Rule Application

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2.0 ASSESSMENT

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

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Enclosures:

1.0 DESCRIPTION

2.0 ASSESSMENT

3.0 REGULATORY ANALYSIS

RESPONSE

RESPONSE

1.0 DESCRIPTION

2.0 ASSESSMENT

Applicable Code Edition and Addenda

Applicable Code Requirement

Reason for Request

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