ML102430164

Supplemental Information for Proposed License Amendment Request Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program

ML102430164
Person / Time
Site:	Surry
Issue date:	08/23/2010
From:	Hartz L Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
10-183A, TSTF-425, Rev 3
Download: ML102430164 (42)

Text

10 CFR 50.90 VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 23, 2010 U.S. Nuclear Regulatory Commission Serial No.

10-183A Attention: Document Control Desk NL&OS/ETS R1 Washington, D.C. 20555 Docket Nos. 50-280/281 License Nos. DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNITS 1 AND 2 SUPPLEMENTAL INFORMATION FOR PROPOSED LICENSE AMENDMENT REQUEST REGARDING RISK-INFORMED JUSTIFICATION FOR THE RELOCATION OF SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO A LICENSEE CONTROLLED PROGRAM (ADOPTION OF TSTF-425, REVISION 3)

In a letter dated March 30, 2010 (Serial No.10-183), Dominion requested amendments, in the form of changes to the Technical Specifications (TS) to Facility Operating License Numbers DPR-32 and DPR-37, for Surry Power Station Units 1 and 2, respectively. The proposed amendments will modify Surry TS by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." In a July 29, 2010 phone call with the NRC staff to discuss the application of TSTF-425 to the Surry TS, the NRC staff requested additional information to support the amendment request. This included: 1) the clarification of the proposed relocated surveillance requirements contained in Section 3.0 of the Surry TS and 2) assurance that the surveillance frequencies relocated from the Surry TS are within the scope of TSTF-425 and the associated NRC SER for the TSTF.

Dominion has re-evaluated the surveillance requirements and associated frequencies in Sections 3.0 and 4.0 of the Surry TS and is retracting all surveillance frequencies in Section 3.0 as well as two surveillance frequencies in Section 4.0 from consideration in the proposed amendment. Attachment 1 provides a list of the surveillance frequencies and the associated TS pages that are being retracted or replaced to reflect these changes.

Subsequent to the March 30, 2010 Dominion submittal, the NRC issued additional guidance on acceptable Bases wording regarding the discussion of the basis for surveillance frequencies. Dominion has reviewed this additional guidance and is providing a revision to its proposed Bases changes consistent with the most recent NRC and industry guidance. also provides a list of the affected TS Bases pages. provides the marked-up pages reflecting changes associated with the surveillance frequencies being retracted from consideration and the corrected TS Bases. to this letter provides a revised Attachment 4 from the March 30, 2010 letter

[TSTF-425 (NUREG-1431) versus Surry TS Cross-Reference] which identifies the Surry TS surveillance frequencies that are being relocated from TS. In addition, Dominion has S(cLQ

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 2 of 3 confirmed that the surveillance frequencies identified in Attachment 3 to this letter are within the scope of TSTF-425 and can be relocated from the Surry TS.

The information provided in this letter does not affect the conclusion of the significant hazards consideration discussion provided in the Dominion letter dated March 30, 2010 (Serial No.10-183) for Surry.

Dominion continues to request approval of the proposed license amendments by April 1, 2011, with the amendment being implemented within 120 days.

If you have any questions or require additional information, please contact Mr. Thomas Shaub at (804) 273-2763.

Very truly yours, Leslie N. Hartz Vice President - Nuclear Support Services Attachments:

1. Surveillance Frequencies Retracted From Consideration and Correction to Bases to Address Basis of Surveillance Frequencies

2. Replacement Marked-up TS and Bases Pages

3. Revised TSTF-425 (NUREG-1431) vs. Surry TS Cross-Reference Table Commitments made in -this letter: None COMMONWEALTH OF VIRGINIA

)

COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Leslie N. Hartz, who is Vice President - Nuclear Support Services, of Virginia Electric and Power Company. She has affirmed before me that she is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of her knowledge and belief.

Acknowledged before me this _r__

day of 2WU-/

,2010.

My Commission Expires:

L15Obs

- --_ _ _LT__-

-_ -u Notary Public 4

GINGER LYNN MELTON IX l wO-scofi 5iol.Q a Yl&otrj 'f Ul ic I

Notary Public N1 Ct L. CIIcd.

I Commonwealth of Virginia I

310847 My Commkision Expires Apr 30. 2013 I

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 3 of 3 cc:

U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 NRC Senior Resident Inspector Surry Power Station Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS ATTACHMENT 1 Surveillance Frequencies Retracted From Consideration and Correction to TS Bases To Address Basis for Surveillance Frequency VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNITS 1 AND 2

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 1 of 2 Proposed License Amendment Request Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)

TS Surveillance Frequencies Being Retracted The following surveillance frequencies are being retracted from Dominion's License Amendment Request (LAR) dated March 30, 2010 (Serial No.10-183).

All of the Surveillance frequencies located in Section 3.0 and two surveillance frequencies in Section 4.0 are being retracted from the LAR. The scope of the LAR is limited to the fixed periodic surveillance frequencies in Section 4.0 of the Surry TS.

The two replacement pages for Section 4 are being provided since there are other proposed changes on those pages.

TS Surveillance Remove TS Page Insert Revised TS Page Section 3.0 3.1.G.1.b 3.1-23 3.1.G.1.c.(5) 3.1-23a 3.12.B.2 and 3 3.12-4 3.12.B.4.d.(2) 3.12-6 3.12.C.3.b.2) 3.12-9 3.12.F.1.a and b 3.12-12A 3.12 Bases Discussion 3.12-20 3.16.B.1.a.1 3.16-2 3.16.B.1.b.4.b and c 3.16-3 Section 4.0 Table 4.1-2A, Item 20 4.1-9d 4.1-9d 4.10.B 4.10-1 4.10-1

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 2 of 2 Surveillance Frequency Bases Pages - Surry TS In Attachment 1, Section 2.2, Item 3 of our March 30, 2010 letter, Dominion identified a deviation from Technical Specification Task Force-425 associated with the proposed Bases wording.

Subsequent to the Dominion March 30, 2010 submittal, the NRC issued additional guidance on acceptable Bases wording regarding the discussion of the basis for surveillance frequencies (ADAMS ML100990099).

In addition, several discussions have taken place between the NRC and Technical Specification Task Force (TSTF) to develop the appropriate wording of the Bases. Dominion has reviewed this additional guidance and is providing a revision to its proposed Bases changes consistent the latest guidance from the NRC and TSTF.

The following Bases words will be used to discuss the basis for surveillance frequencies consistent with the NRC guidance:

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

The following Bases pages have been revised. Please incorporate the following pages into the March 31, 2010 submittal to complete the review of the proposed LAR.

Remove TS Bases Paqe 4.1-3 4.1-5 4.5-4 4.6-5 4.8-3 4.10-2 4.10-3 4.11-4 4.12-6 4.13-2 4.18-1 Insert Revised TS Bases Page 4.1-3 4.1-5 4.5-4 4.6-5 4.8-3 4.10-2 4.10-3 4.11-4 4.12-6 4.13-2 4.18-1 After NRC approval of the LAR and as part of the LAR implementation, the existing Surry Bases information describing the basis for the relocated Surveillance Frequencies will also be relocated to the Surry Surveillance Frequency Control Program.

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - LAR.to Relocate Surveillance Frequencies from TS ATTACHMENT 2 Replacement Marked-up TS and Bases Pages

TS 4.1-3 O5-31-66 Other channels are subject only to the "drift" errors induced within the instrumentation itself and, consequently, can tolerate longer intervals between calibration. Process systems instrumentation errors resulting from drift within the individual instruments are normally negligible.

During the interval between periodic channel tests and 4&H-f check of each channel, a comparison between redundant channels will reveal any abnormal condition resulting from a calibration shift, due to instrument drift of a single channel.

During the periodic channel test, if it is deemed necessary, the channel may be tuned to compensate for the calibration shift. However, it is not expected that this will be required at any fixed or frequent interval.

Thus, minitimu: m alibratian f*e.uenei@. of one r

pe.r day for the nuclear flux (power levql) ehatnittl, and oneeC perL 18 menths for therces s ystein Jchannel are considered acceptable.

Testing 4

The OPERABILITY of the R actor Trip System and ESFAS instrumentation systems and interlocks ensures th t 1) the associated ESF action and/or reactor trip will be initiated when the param er monitored by each channel or combination thereof exceeds its setpoint, 2) tte specified coincidence logic and sufficient redundancy are maintained to perm a channel to be out of service for testing or maintenance consistent with maintai ing an appropriate level of reliability of the RTS and ESFAS instrumentation, and ) sufficient system functional capability is available from diverse parameters.

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

Amendment Nos. :24 ! and 24 6

TS 4.1-5 The refueling water storage tank is sampled weekly for C1-and/or F-contaminations. Weekly sampling is adequate to detect any inleakage of contaminated water.

Main Control Room/Emergency Switchgear Room (MCR/ESGR) Envelope Isolation Actuation Instrumentation The MCR/ESGR Envelope Isolation Actuation function provides a protected \\

environment from which operators can control the unit following an uncontrolled release of radioactivity. A functional check of the Manual Actuation function is performec~vcry 4_ ma, nhs. The test fiequency is based on the known reliability The Surveillance Requirement will ensure that the two train Sf the MCR/ES( R envelope isolation dampers close upon manual actuation o the MCR/ESG Envelope Isolation Actuation Instrumentation and that the su ly and exhau t fans in the normal ventilation system for the MCR/ESG envelope shut own, as well as adjacent area ventilation fans.

Automatic ctuation of t e MCR/ESGR Envelope Isolation Actuation Instrumentati n is confirmed s part of the Logic.Channel Testing for the Safety Injection systeb at the frequtncy specified in the Surveillance Frequency Control Pressurizer PORV, PORV Blo3 Valve, and PORV Backup Air Supply The safety-related, seismic RV backup air supply is relied upon for two functions - mitigation of a desi n basis steam generator tube rupture accident and low temperature overpressure rotection (LTOP) of the reactor vessel during startup and shutdown. The surv illance criteria are based upon the more limiting requirements for the backup ar supply (i.e. more PORV cycles potentially required to perform the mitigatio fun'ction), which are associated with the LTOP function.

The PORV backup air supply sy em is provided with a calibrated alarm for low air pressure. The alarm is located in the control room. Failures such as regulator drift and air leaks which result in ow pressure can be easily recognized by alarm or annunciator action. A periodic uarterly verification of air pressure against the surveillance limit supplements his type of built-in surveillance. Based on experience in operation, the mini mi checking frequencies set forth are deemed adequate.

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

Amendment Nos. -266 and -26

Replace each marked through surveillance frequency in the Frequency column with "SFCP" DESCRIPTION

19. Primary Coolant System

20. Containment Purge MOV Leakage

21.

Deleted

22. RCS Flow

23. Deleted TABLE 4.1-2A(CONTINUED)

S*-

MINIMUM FREQUENCY FOR EQUIPMENT TESTS TEST FREQUENCY Functional

1. Periodic leakage testing(a)(b) on each valve listed in Specification 3.1.C.5.a shall be accomplished prior to entering POWER OPERATION after every time the plant is placed in COLD SHUTDOWN for refueling, after each time the plant is placed in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, and prior to returning the valve to service after maintenance, repair or replacement work is performed.

Functional Semi-Annual (Unit at power or shutdown) if purge valves are operated during interval(c)

UFSAR SECTION REFERENCE 14 Flow > 273,000 gpm Once per 18 months (a)"-sTatisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in acco ce with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the le e criteria.

(b) Minimum differen test pressure shall not be below 150 psid.

(c)

Refer to Section 4.4 for a tance criteria.

See Specification 4.1.D.

z H

-p0-

TS 4.5-4 4-+85"1 7 The recirculation spray pumps outside the containment have the capability of being dry-run and flow tested. The test of an outside recirculation spray pump is performed by closing the containment sump suction line valve and the isolation valve between the pump discharge and the containment penetration. This allows the pump casing to be filled with water and the pump to recirculate water through a test line from the pump discharge to the pump casing.

With a system flush conducted to remove particulate matter prior to the installation of spray nozzles and with corrosion resistant nozzles and piping, it is not considered credible that a significant number of nozzles would plug during the life of the unit to reduce the effectiveness of the subsystems. Therefore, an inspection or air or smoke test of the nozzles following maintenance which could cause nozzle blockage is sufficient to indicate that plugging of the nozzles has not occurred.

The spray nozzles in the refueling water storage tank provide means to ensure that there is no particulate matter in the refueling water storage tank and the containment spray subsystems which could plug or cause deterioration of the spray nozzles. The nozzles in the tank are identical to those used on the containment spray headers. The flow test of the containment spray pumps and recirculation to the refueling water storage will indicate any plugging of the nozzles by a reduction of flow through the nozzles.

Periodic inspections of containment sump components ensure that the components are unrestricted and stay in proper operating condition. The 1t8

.i.n.. fL.qu*,,y. is baseo o(in th need toE performA thi-S srelac undear the eondlitions that apply duoring a Unit 0utage andI On the nOeed to ha-pe Aprpgr to th---Ie loation. Th-is frequency has been found to be sufficient to detectabora degradation and is confirmed by oper.ating @experience.

References FSAR Section 6.3.1, Containment Spray Pumps FSAR Section 6.3.1, Recirculation Spray Pumps IThe Surveillance Frequency is controlled under the Surveillance Frequency Control Program. I Amendment Nos.,255" and 254

TS 4.6-5 Basis The tests specified are designed to demonstrate. that the diesel generators will provide power for operation of essential safeguards equipment. They also assure that the emergency diesel generator system controls and the control systems for the safeguards equipment will function automatically in the event of a loss of normal station service p in the Surveillance Frequency Control Program The testing frequency specified will be often enough to identify and correct any mechanical or electrical deficiency before it can result in a system failure. The fuel supply and starting circuits and controls are continuously monitored and any faults are alarm indicated. An abnormal condition in these systems would be signaled without having to place the diesel generators themselves on test.

Station batteries ay deteriorate with time, but precipitous failure is extremely unlikely. TFhe-of.a..l...e........

s.................

beor In addition alarms have been provided to indicate low batt ry voltage and low current from th inverters which would make it extremely unlikely that dete ioration would go unnoticed.

Emergency diesel enerator n

.. e.

Gtrated by experience The equalizing charge, as recommended by the anufacturer, is vital to maintaining the ampere-hour capability of the battery. As a check up n the effectiveness of the equalizing charge, the battery shall be loaded rather heavily and the vol age monitored as a function of time. If a cell has The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

Unit No. 1 Amendment No. 44-Unit No. 2 Amendment No. 40-

TS 4.8-3 02-23a-06 Basis The correct alignment for manual, power operated, and automatic valves in the Auxiliary Feedwater System steam and water flowpaths, including the cross-connect flowpath, will provide assurance that the proper flowpaths exist for system operation. This position check does not include: 1) valves that are locked, sealed or otherwise secured in position since they are verified to be in their correct position prior to locking, sealing or otherwise securing; 2) vent, drain or relief valves on those flowpaths; and, 3) those valves that

/r cannot be inadvertently misaligned such as check valves. This surveillance does not require any testing or valve manipulation. It involves verification that those valves capable of being mispositioned are in the correct position.

Valves in the auxiliary feedwater flowpaths to th steam generators and cross-connect flow path are tested periodically in accordance wi h the Inservice Testing Program. The auxiliary feedwater pumps are tested periodically i accordance with the Inservice Testing Program to. demonstrate operability. Verification f the developed head of each auxiliary feedwater pump ensures that the pump perf rmance has not degraded. Flow and differential head tests are normal inservice testin requirements. Because it is sometimes undesirable to introduce cold auxiliary feedwate into the steam generators while they are operating, the inservice testing is typically erformed on recirculation flow to the 110,000 gallon Emergency Condensate Storage ank.

Appropriate surveillance and post-maintenanc testing is required to declare equipment OPERABLE. Testing may not be possible ind he applicable plant conditions due to the necessary unit parameters not having been e ablished. In this situation, the equipment may be considered OPERABLE provided tes ng has been satisfactorily completed to the extent possible, and the equipment is not othe wise believed to be incapable.of performing its function. This will allow operation to pr ceed to a condition where other necessary surveillance or post maintenance tests can e completed. Relative to the turbine driven auxiliary feedwater pump, Specification 4.8..3.ý is modified by a note indicating that the developed head test of the turbine driv n pump should be deferred until suitable conditions are established; this deferral i required because there may be insufficient steam pressure to perform the test.

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

Amendment Nos. 246and 2.4

TS 4.10-1 4.10 REACTIVITY ANOMALIES Applicability Applies to potential reactivity anomalies.

Objective To require evaluation of applicable reactivity anomalies within the reactor.

Specification A.

Following a normalization of the computed boron concentration as a function of burnup, the actual boron concentration of the coolant shall be compared fieinth)y with the predicted value. If the difference between the observed and predicted steady-state concentrations reach the equivalent of one percent in reactivity, an evaluation as to the cause of the discrepancy all be made. The provisions of Specification 4.0.4 are not applicable.

B.

During periods of POWER OPERATI at greater than 10% of RATED POWER, the hot channel factors identified in Section 3.12 s 1 be determined during each effective full power month of operation using data from limite ore maps. If these factors exceed their limits, an evaluation as to the cause of the anomaly all be made. The provisions of Specification 4.0.4 are not applicable.

at the frequency specified in the Surveillance Frequency Control Program Amendment Nos.,65-

,t264

TS 4.10-2 12-2-77 DELETED Basis BORON CONCENTRATION To eliminate possible errors in the calculations of the initial reactivity of the core and the reactivity depletion rate, the predicted relation between fuel burnup and the boron concentration necessary to maintain adequate control characteristics must be adjusted (normalized) to accurately reflect actual core conditions. When full power is reached initially, and with the control rod assembly groups in the desired positions, the boron concentration is measured and the predicted curve is adjusted to this point. As power operation proceeds, the measured boron concentration is compared with the predicted concentration, and the slope of the curve relating burnup and reactivity is compared with that predicted. This process of normalization should be completed after about 10% of the total core burnup. Th reafter, actual boron concentration can. be compared with prediction, and the reactivity status of th core can be continuously evaluated. Any reactivity anomaly greater than 1% would be unexp cted, and its occurrence would be thoroughly investigated and evaluated.

The value of 1% is considered a safe limit sinc a shutdown margin of at-least 1% with the most reactive control rod assembly in the fully withdr wn position is always maintained.

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

Unit 1 Amendment No.45--

Unit 2 Amendment No. 34-

TS 4.10-3 1 2-2-77 PEAKING FACTORS A thermal criterion in the reactor core design specified that "no fuel-melting during any anticipated normal operating condition" should occur. To meet the above criterion during a thermal overpower of 118% with additional margin for design uncertainties, a steady state maximum linear power is selected. This then is an upper linear power limit determined by the maximum central temperature of the hot pellet.

The peaking factor is a ratio taken between the maximum allowed linear power density in the reactor to the average value overthe whole reactor. It is of course the average value that determines the operating power level. The peaking factor is a constraint which must be met to assure that the peak linear power density does not exceed the maximum allowed value.

During normal reactor operation, measured peaking factors should be significantly lower than design limits. As core burnup progresses, measured designed peaking factors typically decrease.

A dete:rminti*---

-lof t2L fato*rs during tcach effeLtiv full powe-month of operation is adequate, toe ensi-we that cor-e r-eaeti;'ity ehanges with bur-nup haNvc not sigra fieantly altered pekn factors in an uadverse dir1ciUo.

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

Unit 1 Amendment No.-3 Unit 2 Amendment No. 34-

TS 4.11-4 The system tests demonstrate proper automatic operation of the Safety Injection System. A test signal is applied to initiate automatic operation action and verification is made that the components receive the safety injection signal in the proper sequence. The test may be performed with the pumps blocked, from starting.

The test demonstrates the operation of the valves, pump circuit breakers, and automatic circuitry.

During reactor operation, the instrumentation which is depended on to initiate safety injection is checked periodically, and the initiating circuits are tested in accordance with Specification 4.1. In addition, the active components (pumps and valves) are to be periodically, tested to check the operation of the starting circuits and to verify that the pumps are in satisfactory running order. The test interval is determined in accordance with the Inservice Testing Program. The accumulators are a passive safeguard.

Periodic, inspections of containment sump components ensure that the components are unrestricted and stay in proper operating condition. The

,. 1 8 m "nth fr.equeney based on the need to pefform this, surveillanee undler the ceafditiatns that apply

.ur...g a unit outage antiaftn the need to nave aees, to the

,,eati,,

n.

frequency has be11 found to br sufficient to detet ab...

.. "a" dgiadai and is by operating xeine References UFSAR Section 6.2, Safety Injecti System z

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

Amendment Nos. 255 and 254

at the frequency specified in the Surveillance Frequency Control Program TS 4.12-6 f f _88-84 A pressure drop across the combined H PA filters and charcoal adsorbers of less than 7 inches of water at the system design flo rate will indicate that the filters and adsorbers are not clogged by excessive amounts of reign matter. Operation of the filtration system for a minimum of 15 minutes a revents moisture buildup in the filters and adsorbers.

The frequen y of tests and sample analysis of the degradable components of the system, i.e., the HEP filter and charcoal adsorbers, is based on actual hours of operation to ensure that the perform as evaluated. System flow rates and air distribution do not change unless the venti ation system is radically altered.

If painting, fire, r chemical release occurs such that the HEPA filter or charcoal adsorber could become co taminated from the fumes, chemical, or foreign material, the same tests and sample analys are performed as required for operational use.

The in-place test r ults should indicate a system leak tightness of less than 1 percent bypass leakage for t e charcoal adsorbers and a HEPA efficiency of at least 99.5 percent removal of DOP parti ulates. The heat release from operating ECCS equipment limits the relative humidity of e exhaust air to less than 80 percent even when outdoor air is assumed to be 100 per ent relative humidity and all ECCS leakage evaporates into the exhaust air stream. Met, 1 iodide testing to a penetration less than or equal to 14 percent (applying a safety factor f 2) demonstrates the assumed accident analysis efficiencies of 70 percent for methyl io ide and 90 percent for elemental iodine. This conclusion is supported by a July 10, 2 00 letter from NCS Corporation that stated "Nuclear grade activated carbon, when test din accordance with ASTM D3803-1989 (methyl iodide...)

to a penetration of 15%, is m re conservative than testing the same carbon in accordance with ASTM D3803-1979 (el mental iodine...) to a penetration of 5%.....As a general rule, you may expect the radioi dine penetration through nuclear grade activated carbon to increase from 20 to 100 times hen switching from elemental iodine to methyl iodide testing." Therefore, the efficie cies of the HEPA filters and charcoal adsorbers are demonstrated to be as specifie at flow rates, temperatures, velocities, and relative humidities which are less than the esign values of the system, the resulting doses will be less than or equal to the limrits spe *fied in 10 CFR 50.67 or Regulatory Guide 1.183 for f'

the accidents analyzed. The demons ation of bypass 1% and demonstration of 86 percent methyl iodide removal efficiency wi 1 assure the required capability of the adsorbers is met or exceeded.

Amendment Nos. Bases IThe Surveillance Frequency is under the Surveillance Frequency Control Program.

TS 4.13-2 IThe Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

Steady state operation is required to perform a proper inventory balance since calculations during maneuvering are not useful. For RCS operatio al LEAKAGE determination by water inventory balance, steady state is defined as stable RCS p essure, temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and R P seal injection and return flows.

An early warning of pressutre boundary LEAKAG or unidentified LEAKAGE is provided by the automatic systems that monitor the containment tmosphere radioactivity and the containment sump level. It should be noted that LEAKAGE pa t seals and gaskets is not pressure boundary LEAKAGE. These leakage detectio'n systems are sp ified in the TS 3.1.C Bases.

Note 2 states that this SR is not applicable to Vpri ary to secondary LEAKAGE because LEAKAGE of 150 gallons per day cannot be measur d accurately by an RCS water inventory balance.

of early,,,akag.e dt-ei ihe prev.ntion of acci*ents.,

SR 4.13.B This SR verifies that primary to secondary LEAKAGE is less than or equal to 150 gallons per day through any one SG, with the following exception. The primary to secondary LEAKAGE for, the Unit 1 B steam generator will be limited to 20 gallons per day during Operating Cycle 23.

Satisfying the primary to 'secondary LEAKAGE limit ensures that the operational LEAKAGE performance criterion in the Steam Generator Program is met. If this SR is not met, compliance with LCO 3.1.H, "Steam Generator Tube Integrity," should be evaluated. The 150 gallons per day limit is measured at room temperature as described in Reference 4. The operational LEAKAGE rate limit applies to LEAKAGE through any one SG.

If it is not practical to assign the LEAKAGE to an individual SG, all the primary to secondary LEAKAGE should be conservatively assumed to be from one SG; for Unit 1 that leakage should be assumed to be through the B steam generator for Operating Cycle 23. The surveillance is 1 modified by a Note, which states that the Surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation. For RCS primary to secondary LEAKAGE determination, steady state is defined as stable RCS-pressure, temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flows.

T,* surveillance 72e i a 4.......s...

inte al to trend primary to secondar-'

LEAKAGE -.nd re-egnizes the impertfanee of ear-ly leakage deteetion in the pr-eventiont of aeeidets. 'erimary to secondary LEAKAGE is determined using continuous process radiation monitors or radioche dance with the EPRI guidelines (Ref. 4).

IThe Surveillance Frequency is controlled under the Surveillance Frequency Control Program. I Amendment Nos. 264ad-250

in accordance with the frequency TS 4.18-1

[

specified in the Surveillance00-0 Frequency Control Program.

4.18 MAIN CONTROL ROOM/EMERGENCY VITCHGEAR ROOM (MCR/ESGR)

EMERGENCY VENTILATION SYSTEM (EVS)'

SIN A. Operate each MCRfESGR EVS train for > 15 minut na)

.B. Perform required Control Room Air Filtration System Testing in accordance with TS 4.20.

C. Perform required MCR/ESGR envelope unfiltered air inleakage testing in accordance with the MCRIESGR Envelope Habitability Program.

BASES SURVEILLANCE REQUIREMENTS (SR)

SR 4.18.A Standby systems should be checked periodically to efisure that they function properly. As the en'.iro....And normal operating conditions on this system.ar not t4 ere teoin..

eh traitn once e

.er.y mo.nth pr..id.s an adequate he.k of this system. Systems without heaters need only be operated for 5, 15 minutes to demonstrate the function of the system. The 31 day frequency is based on the reliability of the equipment and the two train redundancy. Operation of the MCRIESGR EVS trains shall be initiated manually from the MCR.

SR 4.18.B1 This SR verifies that the required Control Room Air Filtration Sys m testing is performed in accordance with Specification 4.20. Specification 4.20 includes t ting the performance of the HEPA filter, charcoal adsorber efficiency, minimum flow rate, a the physical properties of the activated charcoal. Specific test frequencies and additional in rmation are discussed in detail in TS 4.20.

SR 4.18.C This SR verifies the OPERABILITY of the MCR/ SGR envelope boundary by testing for unfiltered air inleakage past the MCR/ESGR e elope boundary and into the MCR/ESGR envelope. The details of the testing are specifi d in the MCR/ESGR Envelope Habitability Program (TS 6.4.R).

IThe Surveillance Frequency is controlled under the Surveillance Frequency Control Program. I Amendment Nos. 260,v4Q69

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS ATTACHMENT 3 Revised TSTF-425 (NUREG-1431) vs. Surry TS Cross-Reference VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNITS 1 AND 2

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 1 of 10 CROSS REFERENCE NUREG-1431 TS SURVEILLANCE REQUIREMENTS TO SURRY TS SURVEILLANCE REQUIREMENTS RELOCATED Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS Shutdown margin Verify SDM SR 3.1.1.1 Core Reactivity Verify Measured Core Reactivity within Predicted Value SR 3.1.2.1 TS 4.1O.A Rod Position Verify Rod Position - Alignment SR 3.1.4.1 TS 4.1.A/Table 4.1-1, Item 9 Verify Rod Movement SR 3.1.4.2 TS 4.1.A/Table 4.1-2A, Item 2 TS 4.1.A/Table 4.1-2A, Verify Rod Drop Time te 1 Item 1 Shutdown Bank Verify Alignment SR 3.1.5.1 TS 4.1.A/Table 4.1-1, Item 9 Control Bank Insertion limit Verify Limits SR 3.1.6.3 Verify Control Bank Rod Sequence and Overlap SR 3.1.6.4 Rod Position Indication Calibration of RPI

-TS 4.1.A/Table 4.1-1, Item 9 Physics Test Exceptions RCS Loop Temperature SR 3.1.8.2 Verify Thermal Power SR 3.1.8.3 Verify SDM SR 3.1.8.5 Verify AFD Fo(Z) Limits Verify Fo(Z) limits SR 3.2.1.1 Verify Fo (Z) limits SR 3.2.1.2 N

FAH Limits N

Verify FAH (Z) limits SR 3.2.2.2 AFD Limits Verify AFD Limit SR 3.2.3.1 QPTR Verify QPTR by calculation SR 3.2.4.1 Verify QPTR w/ incore detectors SR 3.2.4.2 RPS Instrumentation TS 4.1./Tlable 4.1-1 Channel Check SR 3.3.1.1 Ce Column Check Column Perform Calorimetric - actual power adjust if > 3%

SR 3.3.1.2 TS 4.1.A/Table4.1-1, Item 1 TS 4.1.A/Table 4.1-1, Compare and Adjust NIS to Incore SR 3.3.1.3 Ite 1 Item 1 TS 4.1.AFTable 4.1-1, TADOT - Rx Trip Breakers SR 3.3.1.4 Ite 30 Item 30 Actuation Logic Test SR 3.3.1.5 TS 4. 1.A/Table 4.1 -1, -

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 2 of 10 Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS Item 26 Calibrate NIS to Incore SR 3.3.1.6 TS 4.1.A/Table 4.1-1, Item 1 TS 4.1.Ai-rable 4.1-1, COT 92 days SR 3.3.1.7 Ite 3 Item 3 TS 4.1.A/Table 4.1-1, COT-Source Range SR 3.3.1.8 Item3 TS 4.1.A/Table 4.1-1 TADOT SR 3.3.1.9 TSt Column Test Column.

Channel Calibration OT/OP AT SR 3.3.1.10 TS 4.1.NTable 4.1-1 Item 4 TS 4.1.A/Table 4.1-1, Channel Calibration SR 3.3.1.11 Item 1

Item 1 Channel Calibration SR 3.3.1.12 TS 4.1.A/Table 4.1-1, Calibration Column TS 4.1.A/Table 4.1-1, COT SR 3.3.1.13TetClm Test Column TS 4.1.AFTable 4.1-1, TADOT SR 3.3.1.14 TS Column Test Column Response Time SR 3.3.1.16 ESFAS Instrumentation TS 4.1.A/Table 4.1-1 Channel Check SR 3.3.2.1 Check Column Actuation Logic Test (92 days)

SR 3.3.2.2 TS 4.1.A/Table 4.1-1 Actuation Logic Test (31 days)

SR 3.3.2.3 ITe 26 Item 26 Master Relay Test SR 3.3.2.4 TS 4.1.A/Table 4.1-1 COT SR 3.3.2.5TetClm Test Column TS 4.11.C.5.a &b; Table Slave Relay Test SR 3.3.2.6 4.1-2A 4.1-2A TS 4.1.A/Table 4.1-1 TADOT SR 3.3.2.7 TS t Column Test Column TS 4.1.A/Table 4.1-1 TADOT SR 3.3.2.8 T

/al Test Column Channel Calibration SR 3.3.2.9 aratio Column Calibration Column Time Response SR 3.3.2.10 PAM Instrumentation PAM Channel Check SR 3.3.3.1 TS 4.1.A/Table 4.1-2 PAM Channel Calibration SR 3.3.3.2 TS 4.1.A/Table 4.1-2 Remote Shutdown System Channel Check SR 3.3.4.1 TS 4.1.AFTable 4.1-2 Control and Transfer Switch Test SR 3.3.4.2 Channel Calibration SR 3.3.4.3 TS 4.1.A/Table 4.1-2 SR 3.3.4.4 TADOT of Reactor Trip Breaker LOP EDG Start Instrumentation Channel Check SR 3.3.5.1

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies-from TS Page 3 of 10 Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS TS 4.1.A/Table 4.1-1 TADOT SR 3.3.5.2 Ie 3.a Item 33.a TS 4.1.A/Table 4.1-1 Channel Calibration SR 3.3.5.3 Ie

3. b Item 33.b Containment Purge and Vent Isolation Channel Check SR 3.3.6.1 Actuation Logic Test SR 3.3.6.2 Master Relay Test SR 3.3.6.3 Actuation SR 3.3.6.4 Master Relay Test SR 3.3.6.5 COT SR 3.3.6.6 Slave Relay Test SR 3.3.6.7 TADOT SR 3.3.6.8 Channel Calibration SR 3.3.6.9 CREFAS Channel Check SR 3.3.7.1 COT SR 3.3.7.2 TS 4.1.B/Table 4.1-2A Actuation Logic Test SR 3.3.7.3 Ite 15 Item 15 Master Relay Test SR 3.3.7.4 Actuation Logic Test SR 3.3.7.5 Master Relay Test SR 3.3.7.6 Slave Relay Test SR 3.3.7.7 TADOT SR 3.3.7.8 Channel Calibration SR 3.3.7.9 FBACS Actuation Instrumentation Channel Check SR 3.3.8.1 Note 1 COT SR 3.3.8.2 Note 1 Actuation Logic Test SR 3.3.8.3 Note 1 TADOT SR 3.3.8.4 Note 1 Channel Calibration SR 3.3.8.5 Note 1 BDPS Channel Check SR 3.3.9.1 Note 1 COT SR 3.3.9.2 Note 1 Channel Calibration SR 3.3.9.3 Note 1 Waste Gas Decay Tanks (Surry Specific)

Test and Calibrate the Oxygen Monitor TS 4. 1.AlTable 4.1-1A, RCS Press Temp & Flow Limits Verify Pressurizer Pressure SR 3.4.1.1 Verify RCS Temperature SR 3.4.1.2 Verify RCS total Flow SR 3.4.1.3 TS.4.1.A/Table 4.1-2A Item 22 Verify RCS Total Flow w/ Heat Balance SR 3.4.1.4 RCS Minimum Temp for Criticality Verify each Loop SR 3.4.2.1

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental-Information - Relocate Surveillance Frequencies from TS Page 4 of 10 Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS RCS Temperature, Pressure, Verify Limits SR 3.4.3.1 Loop Operation - Modes 1 and 2 Verify loop operating SR 3.4.4.1 Loop Operation - Mode 3 Verify loop operating SR 3.4.5.1 Verify Steam Generator water Level > 17%

SR 3.4.5.2 Verify Breaker Alignment and Power Available SR 3.4.5.3 Loop Operation - Mode 4 Verify Loop Operation - Mode 4 SR 3.4.6.1 Verify Steam Generator water Level > 17%

SR 3.4.6.2 Verify Breaker Alignment and Power Available SR 3.4.6.3 Loop Operation - Mode 5 - Loops Filled Verify loop operating SR 3.4.7.1 Verify Steam Generator water Level > 17%

SR 3.4.7.2 Verify Breaker Alignment and Power Available RHR Pumps SR 3.4.7.3 Verify Loop Operation - Mode 5 - Loops Not Filled Verify RHR Operating SR 3.4.8.1 Verify Breaker Alignment and Power Available RHR Pumps SR 3.4.8.2 Pressurizer Verify Water Level SR 3.4.9.1 Verify Heater Capacity of Required Groups SR 2.4.9.2 Verify Heater banks can be Powered for Emergency Power SR 3.4.9.4 Pressurizer PORVS Cycle each Block Valve SR 3.4.11.1 TS 4.1.B1.1.c Cycle each PORV SR 3.4.11.2 TS 4.1.B.11.a Cycle each SOV Valve and Check Valve on the Air Accumulators in SR 3.4.11-.3 TS 4.1.B.1.b PORV Control Systems Verify PORVs and Block Valves can be Powered from Emergency SR 3.4.11.4 Power Sources Verify PORV Backup Nitrogen Supply Pressure TS 4. 1.B. 1.d Functional Test and Calibration of PORV Backup Air Instrumentation and TS4.1B.1.e Alarm POR V Operational Relief Valve Control System TS 4.1. B/table 4.1-2A, Item 18 LTOP Systems Verify only one LHSI pump is capable of injecting into the RCS.

SR 3.4.12.1 Verify a maximum of one charging pump is capable of injecting into the SR 3.4.12.2 RCS Verify each accumulator is isolated SR 3.4.12.3 Verify each RHR Suction Valve is open for each Relief Valve SR 3.4.12.4 Verify required RCS vent [2.07] square inches open SR 3.4.12.5 Verify PORV block valve is open for each required PORV SR 3.4.12.6 V e rify N it ro g e n P re s s u re Verify RHR Suction Isolation Valve is Locked Open for Required RHR SR 3.4.12.7 Suction Relief Valve.

Channel Calibration SR 3.4.12.9 TS 4.1.B/Table 4.1-2A

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 5 of 10 Technical Specification Section TitlelSurveillance Description*

TSTF 425 SPS Items 16 &18 TS 4.1.B/Table 4.1-2A Verify Setpoint for PORV Backup Air Supply Item 17 Operational Leakage Verify RCS operational Leakage SR 3.4.13.1 TS 4.13.A Verify <150 gpd/SG SR 3.4.13.2 TS 4.13.B RCS PIVs Verify leakage from each is < 0.5 gpm SR 3.4.14.1 RCS Leakage Detection Instrumentation Channel Check SR 3.4.15.1 COT SR 3.4.15.2 Channel Calibration Sump Monitor SR 3.4.15.3 Channel Calibration containment atmosphere radioactivity monitor.

SR 3.4.15.4 Channel Calibration containment air cooler.

SR 3.4.15.5 RCS Specific Activity TS 4.1.C/Table 4.1-2B Verify RCS gross specific activity SR 3.4.16.1 Tte 1

Item 1 TS 4.1.C/Table 4.1-2B Verify reactor coolant Dose Equivalent 1-131 SR 3.4.16.2 Ite 1 Item 1 Tritim AtTS 4.1.C/Table 4.1-2B Determine E Bar SR 3.4.16.3 T

/al 1

Item 1 TS 4.1.C/Table 4.1-2B Tritium Activity T

/a l

1 Item 1 TS 4.1.C/Table 4.1-2B Chemistry CL, F, and 02 T

/al 1

Item 1 Boron Concentration T

/al 1

Item 1 TS 4.1.C/Table 4.1-28 Verify Stack Gas Iodine and Particulate te Item 7 RCS Loop Isolation Valves Verify power remove from Isolation valve SR 3.4.17.2 RCS Loops Test Exceptions Verify power < P-7 SR 3.4.19.1 Accumulators Verify Accumulator isolation valve open SR 3.5.1.1 Verify borated Water Volume SR 3.5.1.2 TS 4.11.B.1.a Verify N2 Pressure SR 3.5.1.3 TS 4.11.B.1.b Verify Boron Concentration SR 3.5.1.4 TS 4.11.B.2 Verify Power removed from isolation valve SR 3.5.1.5 ECCS - Operating Verify Valve Lineup SR 3.5.2.1.1 Verify Manual Valve Position SR 3.5.2.1.2 Verify Piping Sufficiently Full SR 3.5.2.1.3 Verify Automatic Valve Position SR 3.5.2.1.5 TS 4.11.C.5.a Verify Pump Start SR 3.5.2.1.6 TS 4.11.C.5.b Verify Throttle Valve Position SR 3.5.2.1.7 Inspection Sump Components SR 3.5.2.1.8 TS 4.11.C.5.c

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 6 of 10 Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS RWST Verify Water Temperature SR 3.5.4.1 TS 4.11.A. 1 Verify Water Volume SR 3.5.4.2 TS 4.11.A.2.a Verify Boron Concentration SR 3.5.4.3 TS 4.11.A.2.b TS 4.1.C/Table 4.1-2B Verify Chemistry Cl and F te Item 2 Verify Boric Acid Tanks Boron Concentration TS 4.1C/Table 4.1-2 Item 3 Seal Injection Flow Verify throttle Valve Position SR 3.5.5.1 BIT Verify Water Temperature SR 3.5.6.1 Note 1 Verify Water Volume SR 3.5.6.2 Note 1 Verify Water Boron Concentration SR 3.5.6.3 Note 1 Containment Air Locks Verify Interlock Operation SR 3.6.2.2 Containment Isolation Valves Verify Purge Valves Sealed Closed (outside containment)

SR 3.6.3.1 TS 4.1.F.1 Verify Purge Valves Closed (inside containment)

SR 3.6.3.2 Verify Valves Outside Containment in Correct Position SR 3.6.3.3 TS 4.1.G Verify Isolation Time of Valves SR 3.6.3.5 Cycle Weight Loaded Check Valves - 92 days SR 3.6.3.6 Perform Leak Rate Test of Purge Valves SR 3.6.3.7 TS 4.1.B/Table 4.1-2A Verify Automatic Valves Actuate to Correct Position SR 3.6.3.8 Ite 6 Item 6 Cycle Non Testable During Power Weight Loaded Check Valves SR 3.6.3.9 4.5.C Verify Purge Valves Blocked SR 3.6.3.10 Containment Pressure Verify Pressure SR 3.6.4.1 Containment Air Temperature Verify Average Air Temperature SR 3.6.5.1 Spray Systems Verify Valve Position SR3.6.6D.1 TS 4.1.A/Table 4.1-1 Verify Valve Actuation SR 3.6.6D.3 ITe 17 Item 17 TS 4.1.A/Table 4.1-1 Verify Pump Start on Auto Signal SR 3.6.6D.4 Item 17 Verify Nozzle are not Obstructed SR 3.6.6D.5 Verify Operability of Weight-Loaded Check Valves TS 4.5.C Recirculation Spray Verify Casing Cooling Temperature SR 3.6.6E.1 Note 1 Verifying Casing Cooling Volume SR 3.6.6E.2 Note 1 Verify Casing Cooling Boron Concentration SR 3.6.6E.3 Note 1 Verify Valve Position SR 3.6.6E 4 TS 4.1.A/Table 4.1-1 Verify Actuation of Pumps and Valves SR 3.6.6E.6 Item 16 Verify Nozzle are not Obstructed SR 3.6.6E.7

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 7 of 10 Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS Inspect Sump Components TS 4.5.D Verify Operability of Weight-Loaded Check Valves TS 4.5.C Spray Additive System Verify Valve position SR 3.6.7.1 Verify Tank Volume SR 3.6.7.2 TS 4.1.C/Table 4.1-2B Verify Tank Solution Concentration SR 3.6.7.3 Ite 4 Item 4 TS 4.1.B/Table 4.1-2A Actuate Each Flow Path Valve SR 3.6.7.4 Ite 3 Item 3 Verify Spray Additive flow from each solution's flow path SR 3.6.7.5 Iodine Cleanup System Operate train with heaters SR 3.6.11.1 Note 1 Verify train Actuation SR 3.6.11.3 Note 1 Verify Filter Bypass Operation SR 3.6.11.4 Note 1 Main Steam Isolation Valves Actuate Valves SR 3.7.2.2 MFIVs and MFRVs Actuate Valves SR 3.7.3.2 Atmospheric Dump Valves Cycle Dump Valves SR 3.7.4.1 Cycle Block Valves SR 3.7.4.2 AFW Verify Valve Position SR 3.7.5.1 TS 4.8.A.1.a Verify Auto Valve Actuation SR 3.7.5.3 TS 4.8.A.6.a Verify Pump.Auto Actuation SR 3.7.5.4 TS 4.8.A.6.b Emergency Condensate Storage Verify Volume SR 3.7.6.1 Component Cooling Verify Valve Position SR 3.7.7.1 Verify Valve Actuation SR 3.7.7.2 Note 1 Verify Pump Actuation SR 3.7.7.3 Note 1 Service Water Verify Valve Position SR 3.7.8.1 TS 4.1.B/Table 4.1-2A Verify Valve Actuation SR 3.7.8.2 TS 8 and 4.A Items 8 and 14.a and b Verify Pump Actuation SR 3.7.8.3 Note 1 Ultimate Heat Sink TS 4.1,A/Table 4.1-1 Verify Water Level SR 3.7.9.1 Ite 40 Item 40 Verify Water Temperature SR 3.7.9.2 Operate Cooling Tower SR 3.7.9.3

/

Note 1 Verify Fan Actuation SR 3.7.9.4 Note 1 CR Emergency Ventilation Operate Heaters SR 3.7.10.1 Verify Train Actuation SR 3.7.10.3 TS 4.1-2A Item 15 Verify Envelope Pressurization SR 3.7.10.4

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 8 of 10 Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS Operate System > 15 minutes 4.18.A CR Air Condition System Verify Train Capacity SR 3.7.11.1 ECCS PREACS Operate Heaters SR 3.7.12.1 Verify Automatic Train Actuation SR 3.12.3 TS 4.12.A.2 Verify Envelope Negative Pressure SR 3.12.4 Verify Bypass Damper Closure SR 3.12.5 Operate System > 15 minutes TS 4.12.A. 1 Fuel Building Air Cleanup Operate Heaters SR 3.7.13.1 Verify Automatic Train Actuation SR 3.7.13.3 Verify Envelope Negative Pressure SR 3.7.13.4 Verify Bypass Damper Closure SR 3.7.13.5 Penetration Room Air Cleanup System -

Operate Heaters SR 3.7.14.1 Note 1 Verify Automatic Train 'Actuation SR 3.7.14.3 Note 1 Verify Envelope Pressurization SR 3.7.14.4 Note 1 Verify Bypass Damper Closure SR 3.7.14.5 Note 1 Fuel Storage Pool Water Level Verify Water Level SR 3.7.15.1 Fuel Storage Pool Boron Verify Boron Concentration SR 3.7.16.1 TS 4.1.CiTable 4.1-2B Item 5 Secondary Specific Activity Verify Secondary Activity SR 3.7.18.1 Table 4.1-2B Item 6 Radioactive Gas Storage Monitoring System (Surry Specific)

Verify radioactive material in each gas storage tank TS 4.9.B AC Sources -Operating Verify Breaker Alignment Offsite Circuits

'SR 3.8.1'.1 Verify EDG Starts - Achieves Voltage & Frequency SR 3.8.1.2 TS 4.6.A.1.a Synchronize and Load for > 60 minutes SR 3.8.1.3 TS 4.6.A.1.a Verify Day Tank Level SR 3.8.1.4 Remove Accumulate Water for Day Tank SR 3.8.1.5 Verify Operation of Transfer Pump SR 3.8.1.6 TS 4.6.A.1.c Verify EDG Starts - Achieves Voltage & Frequency in 10 seconds SR 3.8.1.7 TS 4.6.A.1.b Verify Manual Transfer of AC power Sources - Offsite Sources SR 3.8.1.8 TS 4.6.A.1.a Verify Largest Load Rejection SR 3.8.1.9 Verify EDG Does Not Trip with Load Rejection SR 3.8.1.10 Verify De-energize, Load Shed and Re energize Emergency Bus SR 3.8.1.11 TS 4.6.A.1.b Verify EDG Start on ESF Signal SR 3.8.1.12 TS 4.6.A.1.b Verify EDG Noncritical Trips SR 3.8.1.13 TS 4.6.A.1.b Run EDG for 24 Hours SR 3.8.1.14 Verify EDG Starts - Achieves Voltage & Frequency SR 3.8.1.15 Verify EDG Synchronizes with offsite power and transfers load SR 3.8.1.16 TS 4.6.A. 1.a

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 9 of 10 Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS Verify Test Mode is Overrode on ESF Signal SR 3.8.1.17 Verify Load Sequencers are with Design Tolerance SR 3.8.1.18 TS 4.6.A.1.b Verify EDG Start on Loss of Offsite Power SR 3.8.1.19 TS 4.6.A.1.b Verify when started Simultaneously each EDGs reach rated Voltage and SR 3.8.1.20 Frequency EDG inspection TS 4.6.A.1.d Diesel FO and Starting Air TS 4. 1.BITable 4.1-2A, Verify FO Storage Tank Volume SR 3.8.3.1 Item 11 Verify Lube Oil Inventory SR 3.8.3.2 Verify EDG Start Air Receive Pressure SR 3.8.3.4 Check and Remove Accumulate Water from FO Tanks SR 3.8.3.5 DC Sources Operating Station and EDG Batteries Verify Battery Terminal Voltage SR 3.8.4.1 Verify Station Battery Chargers Capable of Supplying [x]Amp for SR 3.8.4.2

[y]Hours Perform Battery Service Test SR 3.8.4.3 Clean and Coat Station and EDG Battery Terminals TS 4.6.C.1.f TS 4.6.D.1.e Perform Simulated Load Test TS 4.6.C.1.e TS 4.6.D.1.d Compare Battery Voltage and Current w/out Battery charger connected TS 4.6.C.1.d Battery Parameters Station and EDG Batteries Verify each Battery Float Current is < [2] amps.

SR 3.8.6.1 TS 4.6.C.1.b Verify each Battery Pilot Cell Voltage is >[2.07] V SR'3.8.6.2 TS 4.6.D.1.b TS 4.6.D.1.b Verify each Battery Cell Electrolyte Level is > to Minimum Design Limits.

SR 3.8.6.3 TS 4.6.D.1.c TS 4.6. D. 1.c TS 4.6.C.1.a and c Verify each Battery Pilot Cell Temperature > to Minimum Design Limits.

SR 3.8.6.4 TS 4.6.D.l.a and c TS 4.6.D.1 !.a and c TS 4.6.C.1.b Verify Each Battery Connected Cell Voltage is>[2.07] V.

SR 3.8.6.5 TS 4.6.D.1.b TS 4.6.D.1.b Verify Station and EDG Battery Capacity - >80% after Performance Test SR 3.8.6.6 Inverters - Operating Verify Correct Inverter Voltage & Alignment to Required AC Vital Buses.

SR 3.8.7.1 Inverters - Shutdown Verify Correct Inverter Voltage & Alignment to Required AC Vital Buses.

SR 3.8.8.1 Distribution System - Operating Verify Correct Breaker Alignments and Voltage to AC, DC, and AC Vital SR 3.8.9.1 Bus Electrical Power Distribution Subsystems.

Distribution System - Shutdown Verify Correct Breaker Alignments and Voltage to AC, DC, and AC Vital SR 3.8.10.1 Bus Electrical Power Distribution Subsystems.

Boron Concentration Verify Boron Concentration is Within the Limit Specified in COLR SR 3.9.1.1 Primary Grade Water Source Isolation Valves

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 10 of 10 Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS Verify Each Valve that Isolates Unborated Water Sources is Secured in SR 3.9.2.1 the Closed Position Nuclear Instrumentation Perform Channel Check SR 3.9.3.1 Perform Channel Calibration SR 3.9.3.2 Containment Penetrations Verify each Required Containment Penetration is in the Required Status.

SR 3.9.4.1 Verify Each Required Containment Purge and Exhaust Valve Actuates to SR 3.9.4.2 the Isolation Position on an Actuated or Simulated Actuation Signal.

RHR and Coolant Circulation - High Water Level Verify One Loop is in Operation and Circulating Reactor Coolant at a SR 3.9.5.1 Flow Rate of > [2800] gpm.

RHR and Coolant Circulation - Low Water Level Verify One Loop is in Operation and Circulating Reactor Coolant at a SR 3.9.6.1 flow rate of > [2800] gpm.

Verify Correct Breaker Alignment and Indicated Power Available to the SR 3.9.6.2 Required RHR Pump that is Not in Operation.

Refueling Cavity Water Level Verify Refueling Cavity Water Level is >23 ft Above The Top of Reactor SR 3.9.7.1 Vessel Flange.

Miscellaneous Radioactive Material Sources (Surry Specific)

Leak Check sources with > 30 day Half-Life TS 4.16.B. 1.a Leak Check sources exempt from the Surveillance 4.16.a TS 4.16.B. 1.b Note 1 -

This system or function is not included in the Surry design or TS.

Italicized Surveillances are Surry specific surveillances.

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS ATTACHMENT 3 Revised TSTF-425 (NUREG-1431) vs. Surry TS Cross-Reference VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNITS 1 AND 2

Serial No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 1 of 10 CROSS REFERENCE NUREG-1431 TS SURVEILLANCE REQUIREMENTS TO SURRY TS SURVEILLANCE REQUIREMENTS RELOCATED Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS Shutdown margin Verify SDM SR 3.1.1.1 Core Reactivity Verify Measured Core Reactivity within Predicted Value SR 3.1.2.1 TS 4.1O.A Rod Position TS 4.1.A/Table 4.1-1 Verify Rod Position - Alignment SR 3.1.4.1 Item 9 TS 4.1.A/Table 4.1-2A Verify Rod Movement SR 3.1.4.2 Ite 2

Item 2 Verify Rod Drop Time TS 4.1.Table 4.1-2A Item 1 Shutdown Bank TS 4.1.AFTable 4.1-1 Verify Alignment SR 3.1.5.1 Ite 9 Item 9 Control Bank Insertion limit Verify Limits SR 3.1.6.3 Verify Control Bank Rod Sequence and Overlap SR 3.1.6.4 Rod Position Indication Calibration of RPI TS 4.1.A/Table 4.1-1 Item 9 Physics Test Exceptions RCS Loop Temperature SR 3.1.8.2 Verify Thermal Power SR 31.8.3 Verify SDM SR 3.1.8.5 Verify AFD Fo(Z) Limits Verify FQ(Z) limits SR 3.2.1.1 Verify Fý'(Z) limits SR 3.2.1.2 N

FAH Limits N Verify FAH (Z) limits SR 3.2.2.2 AFD Limits Verify AFD Limit SR 3.2.3.1 QPTR Verify QPTR by calculation SR 3.2.4.1 Verify QPTR w/ incore detectors SR 3.2.4.2 RPS Instrumentation Channel Check SR 3.3.1.1 TS 4.1.AITable 4.1-1 Check Column Perform Calorimetric - actual power adjust if > 3%

SR 3.3.1.2 TS 4.1.AFlable 4.1-1 Item 1

Compare and Adjust NIS to Incore SR 3.3.1.3 TS 4.1.A/Table 4.1-1 Item 1 TADOT - Rx Trip Breakers SR 3.3.1.4 TS 4.1.A/Table 4.1-1 Item 30 Actuation Logic Test SR 3.3.1.5 TS 4I.A/Table 4.1-1 Item 26

Serial'No. 10-183A Docket Nos. 50-280/281 Supplemental Information - Relocate Surveillance Frequencies from TS Page 2 of 10 Technical Specification Section Title/Surveillance Description*

TSTF 425 SPS Calibrate NIS to Incore SR 3.3.1.6 TS 4.1.A/Table 4.1-1 Item 1 COT 92 days SR 3.3.1.7 TS 4.1.ArTable 4.1-1 Item 3 COT - Source Range SR 3.3.1.8 TS 4.1.A/Table 4.1-1 Item 3 TADOT SR 3.3.1.9 TS 4.1.Arrable 4.1-1 Test Column

' Channel Calibration OT/OP AT SR 3.3.1.10 TS4.1.A/Table4.1-1 Item 4 Channel Calibration SR 3.3.1.11, TS4.1.A/Table4.1-1 Calibration Column Channel Calibration SR 3.3.1.12 TS 4.1.ANTable 4.1-1 Calibration Column COT SR 3.3.1.13 TS 4.1.A/Table 4.1-1 Test Column

~TS 4.1.A/Table 4.1-1 TADOT SR 3.3.1.14 TSt column Test Column Response Time SR 3.3.1.16 ESFAS Instrumentation Channel Check SR 3.3.2.1 TS 4.1.A/Table 4.1-1 Check Column Actuation Logic Test (92 days)

SR 3.3.2.2 Actuation Logic Test (31 days)

SR 3.3.2.3 TS 4.1.ArTable 4.1-1 Item 26 Master Relay Test SR 3.3.2.4 COT SR 3.312.5 TS 4.1.A/Table 4.1-1 Test Column Slave Relay Test SR 3.3.2.6 TS 4.11.C.5.a &b; Table 4.1-2A STADOT SR 3.3.2.7 TS 4.1.A/Table 4.1-1 Test Column TADOT SR 3.3.2.8 TS 4.1.A/Table 4:1-1 Test Column Channel Calibration SR 3.3.2.9 TS 4.1.A/Table 4.1-1 Calibration Column Time Response SR 3.3.2.10 PAM Instrumentation PAM Channel Check SR 3.3.3.1 TS 4.1.A/Table 4.1-2 PAM Channel Calibration SR 3.3.3.2 TS 4.1.A/Table 4.1-2 Remote Shutdown System Channel Check SR 3.3.4.1 TS 4.1.A/Table 4.1-2 Control and Transfer Switch Test SR 3.3.4.2 Channel Calibration SR 3.3.4.3 TS 4.1.A/Table 4.1-2 TADOT of Reactor Trip Breaker SR 3.3.4.4 LOP EDG Start Instrumentation Channel Check SR 3.3.5.1 TADOT SR 3.3.5.2 TS4.1.ArTable4.1-1 Item 33.a Channel Calibration SR 3.3.5.3 TS 4.1.A/Table 4.1-1 Item 33.b Containment Purge and Vent Isolation

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TSTF 425 SPS Channel Check SR 3.3.6.1 Actuation Logic Test SR 3.3.6.2 Master Relay Test SR 3.3.6.3 Actuation SR 3.3.6.4 Master Relay Test SR 3.3.6.5 COT SR 3.3.6.6 Slave Relay Test SR 3.3.6.7 TADOT SR 3.3.6.8 Channel Calibration SR 3.3.6.9 CREFAS Channel Check SR 3.3.7.1 COT SR 3.3.7.2 Actuation Logic Test SR,3.3.7.3 TS 4.1.B/Table 4.1-2A Item 15 Master Relay Test SR 3.3.7.4 Actuation Logic Test SR 3.3.7.5 Master Relay Test SR 3.3.7.6 Slave Relay Test SR 3.3.7.7 TADOT SR 3.3.7.8 Channel Calibration SR 3.3.7.9 FBACS Actuation Instrumentation Channel Check SR 3.3.8.1 Note 1 COT SR 3.3.8.2 Note 1 Actuation Logic Test SR 3.3.8.3 Note 1 TADOT SR 3.3.8.4 Note 1 Channel Calibration SR 3.3.8.5 Note 1 BDPS Channel Check SR 3.3.9.1 Note 1 COT SR 3.3.9:2 Note 1 Channel Calibration SR 3.3.9.3 Note 1 Waste Gas Decay Tanks (Surry Specific)

Test and Calibrate the Oxygen Monitor TS 4.1.A/Table 4.1-1A RCS Press Temp & Flow Limits Verify Pressurizer Pressure SR 3.4.1.1 Verify RCS Temperature SR 3.4.1.2 TS 4.1.8/Table 4.1-2A Verify RCS total Flow SR 3.4.1.3 Ite 22 Item 22 Verify RCS Total Flow w/ Heat Balance SR 3.4.1.4 RCS Minimum Temp for Criticality Verify each Loop SR 3.4.2.1 RCS Temperature, Pressure, Verify Limits SR 3.4.3.1 Loop Operation - Modes 1 and 2 Verify loop operating SR 3.4.4.1 Loop Operation - Mode 3

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TSTF 425 SPS Verify loop operating SR 3.4.5.1.

Verify Steam Generator water Level > 17%

SR 3.4.5.2 Verify Breaker Alignment and Power Available SR 3.4.5.3 Loop Operation - Mode 4 Verify Loop Operation - Mode 4 SR 3.4.6.1 Verify Steam Generator water Level > 17%

SR 3.4.6.2 Verify Breaker Alignment and Power Available SR 3.4.6.3 Loop Operation - Mode 5 - Loops Filled Verify loop operating SR 3.4.7.1 Verify Steam Generator water Level > 17%

SR 3.4.7.2 Verify Breaker Alignment and Power Available RHR Pumps SR 3.4.7.3 Verify Loop Operation - Mode 5 - Loops Not Filled Verify RHR Operating SR 3.4.8.1 Verify Breaker Alignment and Power Available RHR Pumps SR 3.4.8.2 Pressurizer Verify Water Level SR 3.4.9.1 Verify Heater Capacity of Required Groups SR 2.4.9.2 Verify Heater banks can be Powered for Emergency Power SR 3.4.9.4 Pressurizer PORVS Cycle each Block Valve SR 3.4.11.1

.TS 4.1.B.1.c Cycle each PORV SR 3.4.11.2 TS 4.1..B.1.a Cycle each SOV Valve and Check Valve on the Air Accumulators in SR 3.4.11.3 TS 4.1.B.1.b PORV Control Systems Verify PORVs and Block Valves can be Powered from Emergency SR 3.4.11.4 Power Sources Verify PORV Backup Nitrogen Supply Pressure TS 4. 1.B. 1.d Functional Test and Calibration of PORV Backup Air Instrumentation and TS 4. 1B. 1.e Alarm PORV Operational Relief Valve Control System TS 4.1 B/Table 4.1-2A Item 18 LTOP Systems Verify only one LHSI pump is capable of injecting into the RCS.

SR 3.4.12.1 Verify a maximum of one charging pump is capable of injecting into the SR 3.4.12.2 RCS Verify each accumulator is isolated SR 3.4.12.3 Verify each RHR Suction Valve is open for each Relief Valve SR 3.4.12.4 Verify required RCS vent [2.07] square inches open SR 3.4.12.5 Verify PORV block valve is open for each required PORV SR 3.4.12.6 Verify Nitrogen Pressure Verify RHR Suction Isolation Valve is Locked Open for Required RHR SR 3.4.12.7 Suction Relief Valve.

TS 4.1.B/Table 4.1-2A Channel Calibration SR 3.4.12.9 TS 1 6&18 Items 16 &18 TS 4.1.B/Table 4.1-2A Verify Setpoint for PORV Backup Air Supply Item 17 Operational Leakage Verify RCS operational Leakage SR 3.4.13.1 TS 4.13.A Verify <150 gpd/SG SR 3.4.13.2 TS4.13.B

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TSTF 425 SPS RCS PIVs Verify leakage from each is < 0.5 gpm SR 3.4.14.1 RCS Leakage Detection Instrumentation Channel Check SR 3.4.15.1 COT SR 3.4.15.2 Channel Calibration Sump Monitor SR 3.4.15.3 Channel Calibration containment atmosphere radioactivity monitor.

SR 3.4.15.4 Channel Calibration containment air cooler.

SR 3.4.15.5 RCS Specific Activity Verify RCS gross specific activity SR 3.4.16.1 TS 4.1.CITable 4.1-21 Item 1 TS 4.1.C/Table 4.1-28 Verify reactor coolant Dose Equivalent 1-131 SR 3.4.16.2 Ite 1 Item 1 Tritum ctiityTS 4.1.CiTable4.1-2B Determine E Bar SR 3.4.16.3 T

fal 1

Item 1 Chetium Actvistr y CTS 4.1.C/Table 4.1-2B Item 1 ChemstryCL, an 02TS 4.1.C/Table 4.1-213 ChemstryCL, an 02Item 1

Boron Concentration TS 4.1.C/Table 4.1-26 Item 1 Verify Stack Gas Iodine and Particulate TS 4.1.Cable 4.1-2 Item 7 RCS Loop Isolation Valves Verify power remove from Isolation valve SR 3.4.17.2 RCS Loops Test Exceptions Verify power < P-7 SR 3.4.19.1 Accumulatdrs Verify Accumulator isolation valve open SR 3.5.1.1 Verify borated Water Volume SR 3.5.1.2 TS 4.11.B.1.a Verify N2 Pressure SR 3.5.1.3 TS 4.11.B.1.b Verify Boron Concentration SR 3.5.1.4 TS 4.11.B.2 Verify Power removed from isolation valve SR 3.5.1.5 ECCS - Operating Verify Valve Lineup SR 3.5.2.1.1 Verify Manual Valve Position' SR 3.5.2.1.2 Verify Piping Sufficiently Full SR 3.5.2.1.3 Verify Automatic Valve Position SR 3.5.2.1.5 TS 4.11.C.5.a Verify Pump 'Start SR 3.5.2.1.6 TS 4.11.C.5.b Verify Throttle Valve Position SR 3.5.2.1.7 Inspection Sump Components SR 3.5.2.1.8 TS 4.11.C.5.c RWST Verify Water Temperature SR 3.5.4.1 TS 4.11.A.1 Verify Water Volume SR 3.5.4.2 TS 4.11.A.2.a Verify Boron Concentration SR 3.5.4.3 TS 4.11.A.2.b TS 4.1.C/Table 4.1-2B Verify Chemistry Cl and F te 2

Item 2 Verify Boric Acid Tanks Boron Concentration TS 4.1-.C-able 4.1-21 Item 3

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TSTF 425 SPS Seal Injection Flow Verify throttle Valve Position SR 3.5.5.1 BIT Verify Water Temperature SR 3.5.6.1 Note 1 Verify Water Volume SR 3.5.6.2 Note 1 Verify Water Boron Concentration SR 3.5.6.3 Note 1 Containment Air Locks Verify Interlock Operation SR 3.6.2.2 Containment Isolation Valves Verify Purge Valves Sealed Closed (outside containment)

SR 3.6.3.1 TS 4.1.F.1 Verify Purge Valves Closed (inside containment)

SR 3.6.3.2 Verify Valves Outside Containment in Correct Position SR 3.6.3.3 TS 4.1.G Verify Isolation Time of Valves SR 3.6.3.5 Cycle Weight Loaded Check Valves - 92 days SR 3.6.3.6 Perform Leak Rate Test of Purge Valves SR 3.6.3.7 TS 4.1.B/Table 4.1-2A Verify Automatic Valves Actuate to Correct Position SR 3.6.3.8 Ite 6 Item 6 Cycle Non Testable During Power Weight Loaded Check Valves SR 3.6.3.9 TS 4.5.C Verify Purge Valves Blocked SR 3.6.3.10 Containment Pressure Verify Pressure SR 3.6.4.1 Containment Air Temperature Verify Average Air Temperature SR 3.6.5.1 Spray Systems Verify Valve Position SR3.6.6D.1 Verify Valve Actuation SR 3.6.6D.3 TS 4.1.A/Table 4.1-1 Item 17 Verify Pump Start on Auto Signal SR 3.6.6D.4 TS4.1.ATable 4.1-1 Item 17 Verify Nozzle are not Obstructed SR 3.6.6D.5 Verify Operability of Weight-Loaded Check Valves TS 4.5.C Recirculation Spray Verify Casing Cooling Temperature SR 3.6.6E.1 Note 1 Verifying Casing Cooling Volume SR 3.6.6E.2 Note 1 Verify Casing Cooling Boron Concentration SR 3.6.6E.3 Note 1 Verify Valve Position SR 3.6.6E 4 Verify Actuation of Pumps and Valves SR 3.6.6E.6 TS 4.1I.Atable 4.1-1 Item 16 Verify Nozzle are not Obstructed SR 3.6.6E.7 Inspect Sump Components TS 4.5.D Verify Operability of Weight-Loaded Check Valves TS 4.5.C Spray Additive System Verify Valve position SR 3.6.7.1 Verify Tank Volume SR 3.6.7.2 TS 4.1.C/Table 4.1-2B Verify Tank Solution Concentration SR 3.6.7.3 Item 4

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TSTF 425 SPS TS 4.1,B/Table 4.1-2A Actuate Each Flow Path Valve SR 3.6.7.4 Ite 3 Item 3 Verify Spray Additive flow from each solution's flow path SR 3.6.7.5 Iodine Cleanup System Operate train with heaters SR 3.6.11.1 Note 1 Verify train Actuation SR 3.6.11.3 Note 1 Verify Filter Bypass Operation SR 3.6.11.4 Note 1 Main Steam Isolation Valves Actuate Valves SR 3.7.2.2 MFIVs and MFRVs Actuate Valves SR 3.7.3.2 Atmospheric Dump Valves Cycle Dump Valves SR 3.7.4.1 Cycle Block Valves SR 3.7.4.2 AFW Verify Valve Position SR 3.7.5.1 TS 4.8.A.1.a Verify Auto Valve Actuation SR 3.7.5.3 TS 4.8.A.6.a Verify Pump Auto Actuation SR 3.7.5.4 TS 4.8.A.6.b Emergency Condensate Storage Verify Volume SR 3.7.6.1 Component Cooling Verify Valve Position SR 3.7.7.1 Verify Valve Actuation SR 3.7.7.2 Note 1 Verify Pump Actuation SR 3.7.7.3 Note 1 Service Water Verify Valve Position SR 3.7.8.1 TS 4.1,B/Table 4.1-2A Verify Valve Actuation SR 3.7.8.2, TS 8 and 4.A Items 8 and 14.a and b Verify Pump Actuation SR 3.7.8.3 Note 1 Ultimate Heat Sink TS 4.1,A/Table 4.1-1 Verify Water Level SR 3.7.9.1 ITe 40 Item 40 Verify Water Temperature SR 3.7.9.2 Operate Cooling Tower SR 3.7.9.3 Note 1 Verify Fan Actuation SR 3.7.9.4 Note 1 CR Emergency Ventilation Operate Heaters SR 3.7.10.1 Verify Train Actuation SR 3.7.10.3 TS 4.1-2Altem 15 Verify Envelope Pressurization SR 3.7.10.4 Operate System > 15 minutes TS 4.18.A CR Air Condition System Verify Train Capacity SR 3.7.11.1 ECCS PREACS Operate Heaters SR 3.7.12.1 Verify Automatic Train Actuation SR 3.12.3 TS 4.12.A.2, Verify Envelope Negative Pressure SR 3.12.4

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TSTF 425 SPS Verify Bypass Damper Closure SR 3.12.5 Operate System > 15 minutes TS 4.12.A. 1 Fuel Building Air Cleanup Operate Heaters SR 3.7.13.1 Verify Automatic Train Actuation SR 3.7.13.3 Verify Envelope Negative Pressure SR 3.7.13.4 Verify Bypass Damper Closure SR 3.7.13.5 Penetration Room Air Cleanup System -

Operate Heaters SR 3.7.14.1 Note 1 Verify Automatic Train Actuation SR 3.7.14.3 Note 1 Verify Envelope Pressurization SR 3.7.14.4 Note 1 Verify Bypass Damper Closure SR 3.7.14.5 Note 1 Fuel Storage Pool Water Level Verify Water Level SR 3.7.15.1 Fuel Storage Pool Boron TS 4.1.0/Table 4.1-2B Verify Boron Concentration SR 3.7.16.1 Ite 4

Item 5 Secondary Specific Activity TS 4.1.0/Table 4.1-2B Verify Secondary Activity SR 3.7.18.1 Ite 6 Item 6 Radioactive Gas Storage Monitoring System (Surry Specific)

Verify radioactive material in each gas storage tank TS 4.9.B AC Sources -Operating Verify Breaker Alignment Offsite Circuits SR 3.8.1.1 Verify EDG Starts - Achieves Voltage & Frequency SR 3.8.1.2 TS 4.6.A.1.a Synchronize and Load for > 60 minutes SR 3.8.1.3 TS 4.6.A.1.a Verify Day Tank Level SR 3.8.1.4 Remove Accumulate Water for Day Tank SR 3.8.1.5 Verify Operation of Transfer Pump SR 3.8.1.6 TS 4.6.A.1.c Verify EDG Starts - Achieves Voltage & Frequency in 10 seconds SR 3.8.1.7 TS 4.6.A.1.b Verify Manual Transfer of AC power Sources - Offsite Sources SR 3.8.1.8 TS 4.6.A.1.a Verify Largest Load Rejection SR 3.8.1.9 Verify EDG Does Not Trip with Load Rejection SR 3.8.1.10 Verify De-energize, Load Shed and Re energize Emergency Bus SR 3.8.1.11 TS 4.6.A.1.b Verify EDG Start on ESF Signal SR 3.8.1.12 TS 4.6.A.1.b Verify EDG Noncritical Trips SR 3.8.1.13 TS 4.6.A.1.b Run EDG for 24 Hours SR 3.8.1.14 Verify EDG Starts - Achieves Voltage & Frequency SR 3.8.1.15 Verify EDG Synchronizes with offsite power and transfers load SR 3.8.1.16 TS 4.6.A.1.a Verify Test Mode is Overrode on ESF Signal SR 3.8.1.17 Verify Load Sequencers are with Design Tolerance SR 3.8.1.18 TS 4.6.A.1.b Verify EDG Start on Loss of Offsite Power SR 3.8.1.19 TS 4.6.A.1.b Verify when started Simultaneously each EDGs reach rated Voltage and SR 3.8.1.20 Frequency EDG inspection TS 4.6.A.1.d

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. Page 9 of 10 Technical Specification Section TitlelSurveillance Description*

TSTF 425 SPS Diesel FO and Starting Air TS 4.1.B/Table 4.1-2A, Verify FO Storage Tank Volume SR 3.8.3.1 Ite 11 Item 11 Verify Lube Oil Inventory SR 3.8.3.2 Verify EDG Start Air Receive Pressure SR 3.8.3.4 Check and Remove Accumulate Water from FO Tanks SR 3.8.3.5 Station and DC Sources Operating Stati es EDG Batteries Verify Battery Terminal Voltage SR 3.8.4.1 Verify Station Battery Chargers Capable of Supplying [x]Amp for SR 3.8.4.2

[y]Hours Perform Battery Service Test SR 3.8.4.3 TS 4.6.C.1.f Clean and Coat Station and EDG Battery Terminals TS 4.6.D..

TS 4.6.D.1.e Perform Simulated Load Test TS 4.6.C. 1.e TS 4.6.D.1.d Compare Battery Voltage and Current w/out Battery charger connected TS 4.6.C.1.d Station and Battery Parameters EDG Batteries Verify each Battery Float Current is < [2] amps.

SR 3.8.6.1 TS 4.6.C.1.b Verify each Battery Pilot Cell Voltage is >[2.07] V SR 3.8.6.2 TS 4.6.D.1.b TS 4.6.D.1.b TS 4.6.C.1.c Verify each Battery Cell Electrolyte Level is > to Minimum Design Limits.

SR 3.8.6.3 TS 4.6.D.1.c TS 4.6. D. 1.c TS 4.6.C.1.a and c Verify each Battery Pilot Cell Temperature > to Minimum Design Limits.

SR 3.8.6.4 TS 4.6.0.1.a and c TS 4.6. D. 1.a and c TS 4.6.C.1.b Verify Each Battery Connected Cell Voltage is>[2.07] V.

SR 3.8.6.5 TS 4.6.D.1.b Verify Station and EDG Battery Capacity - >80% after Performance Test SR 3.8.6.6 Inverters - Operating Verify Correct Inverter Voltage & Alignment to Required AC Vital Buses.

SR 3.8.7.1 Inverters - Shutdown Verify Correct Inverter Voltage & Alignment to Required AC Vital Buses.

SR 3.8.8.1 Distribution System - Operating Verify Correct Breaker Alignments and Voltage to AC, DC, and AC Vital SR 3.8.9.1 Bus Electrical Power Distribution Subsystems.

Distribution System - Shutdown Verify Correct Breaker Alignments and Voltage to AC, DC, and AC Vital SR 3.8.10.1 Bus Electrical Power Distribution Subsystems.

Boron Concentration Verify Boron Concentration is Within the Limit Specified in COLR SR 3.9.1.1 Primary Grade Water Source Isolation Valves Verify Each Valve that Isolates Unborated Water Sources is Secured in SR 3.9.2.1 the Closed Position Nuclear Instrumentation Perform Channel Check SR 3.9.3.1 Perform Channel Calibration SR 3.9.3.2 Containment Penetrations

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TSTF 425 SPS Verify each Required Containment Penetration is in the Required Status.

SR 3.9.4.1 Verify Each Required Containment Purge and Exhaust Valve Actuates to 8R 3.9.4.2 the Isolation Position on an Actuated or Simulated Actuation Signal.

RHR and Coolant Circulation - High Water Level Verify One Loop is in Operation and Circulating Reactor Coolant at a SR 3.9.5.1 Flow Rate of > [2800] gpm.

RHR and Coolant Circulation - Low Water Level Verify One Loop is in Operation and Circulating Reactor Coolant at a SR 3.9.6.1 flow rate of > [2800] gpm.

Verify Correct Breaker Alignment and Indicated Power Available to the SR 3.9.6.2 Required RHR Pump that is Not in Operation.

Refueling Cavity Water Level Verify Refueling Cavity Water Level is >23 ft Above The Top of Reactor SR 3.9.7.1 Vessel Flange.

Miscellaneous Radioactive Material Sources (Surry Specific)

Leak Check sources with > 30 day Half-Life TS 4.16.B. 1.a Leak Check sources exempt from the Surveillance 4.16.a TS 4.16.B. 1.b Note 1 -

This system or function is not included in the Surry design or TS.

Italicized Surveillances are Surry specific surveillances.