RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)

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Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)
ML17122A223
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 05/02/2017
From: Kapopoulos E
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/17-0034
Download: ML17122A223 (28)
v • d • e


Text

/_~ DUKE ENERGY~

Serial: RNP-RA/17-0034 MAY 0 2 2017 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 /RENEWED LICENSE NO. DPR-23 Ernest J. Kapopoulos, Jr.

H. B. Robinson Steam Electric Plant Unit 2 Site Vice President Duke Energy 3581 West Entrance Road Hartsville, SC 29550 0 843 857 1701 F: 843 857 1319 Ernie. Kapopo11/os@duke-energy.com MODIFICATION OF REQUEST FOR TECHNICAL SPECIFICATION CHANGE TO CHANGE TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT FREQUENCIES TO SUPPORT 24-MONTH FUEL CYCLES (MF9544)

Dear Sir/Madam:

By letter dated April 3, 2017, Duke Energy Progress, LLC (DEP) requested an amendment to the Technical Specifications (TS) for H. 8. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP) to support 24-month fuel cycle operations. Specifically, this change requested Nuclear Regulatory Commission (NRC) approval for certain HBRSEP TS Surveillance Requirement frequencies that are specified as "18 months" by revising them to "24 months" in accordance with the guidance of Generic Letter 91-04, "Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle," dated April 2, 1991.

It was noted that evaluations of the proposed TS changes listed in Section 3 of the Enclosure were found in either Attachments 6 or 8 except for the following:

TS 3.3.4 Remote Shutdown System SR 3.3.4.2 Verify each required control circuit and transfer switch is capable of performing the intended function Table B 3.3.4-1 Item 1.c SR 3.3.4.4 Perform TADOT of the reactor trip breaker open/closed indication Table B 3.3.4-1 Items 1.b, 1.c TS 3.3.7 CREFS Actuation Instrumentation SR 3.3. 7.4 Perform MASTER RELAY CHECK Table 3.3.7-1 Item 1 SR 3.3.7.5 Perform SLAVE RELAY TEST Table 3.3.7-1 Item 1

U. S. Nuclear Regulatory Commission Serial: RNP-RA/17-0034 Page 2 of 3 TS 3.8.4 DC Sources - Operating SR 3.8.4.2 Verify battery cells, cell plates, and racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance This discrepancy was discussed in a telephone conversation between Mr. Dennis Galvin, NRC, and OEP on April 10, 2017.

DEP confirmed that the five (5) surveillance requirements noted above are currently required to be performed at an 18 month interval. Upon further consideration, the five (5) surveillances will remain at an 18 month frequency and can be omitted from Section 3 of the LAA enclosure. The corrected marked-up and retyped Technical Specifications and Bases pages are included in the Attachments of this letter.

The original submittal contained a reference to "Section 8.5.1," on pages 15 of 393 and 242 of 393. This is a reference to a section in Engineering Change 400739, "RNP 24 Month Fuel Cycle Analysis" that supports the LAA. It was inadvertently carried over into the submittal and should be disregarded. consists of Technical Specifications and license amendment request pages with editorial corrections that were noted in an April 12, 2017 e-mail from Mr. Galvin, NRC, to Mr.

Tony Pilo, DEP.

DEP requests approval of the license amendment request by refueling outage 31, currently scheduled for September 15, 2018, with implementation within 120 days after approval.

Please address any comments or questions regarding this matter to Mr. Tony Pilo, Manager -

Nuclear Regulatory Affairs at (843) 857-1409.

I declare under penalty of perjury that the foregoing is true and correct. Executed on iMA-7

'l..

, 2017.

Sincerely, Ernest J. Kapopoulos, Jr.

Site Vice President EJK/jsk

U.S. Nuclear Regulatory Commission Serial: RNP-RA/17-0034 Page 3 of 3 Attachments:

1. Technical Specifications - Marked-up Pages
2. Technical Specifications - Retyped Pages
3. Technical Specification Bases - Marked-up Pages
4. Technical Specification Bases - Retyped Pages
5. Technical Specifications and License Amendment Request Pages With Editorial Corrections cc: Regional Administrator, NRC Region II Mr. Dennis J. Galvin NRC Project Manager, NRR NRC Resident Inspector, HBRSEP Ms. S. E. Jenkins, Manager, Infectious and Radioactive Waste Management Section (SC)

A. Gantt, Chief, Bureau of Radiological Health (SC)

Alan Wilson, Attorney General (SC)

U.S. Nuclear Regulatory Commission to Serial: RNP-RA/17-0034 4 Pages (including cover page)

ATTACHMENT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES

Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS SR 3.3.4.1 SR 3.3.4.2 SR 3.3.4.3 SR 3.3.4.4 SURVEILLANCE FREQUENCY Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

Verify each required control circuit and transfer 18 months switch is capable of performing the intended function.

---~----~----~----~-----NC>TE---~----------~----~----~----

Neutron detectors are excluded from CHANNEL CALIBRATIC>N.

Perform CHANNEL CALI BRA TIC>N for each required 4&-months instrumentation channel.

Perform T ADC>T of the reactor trip breaker open/closed indication.

18 months HBRSEP Unit No. 2 3.3-34 Amendment No. m-

SURVEILLANCE REQUIREMENTS (continued)

SR 3.3.7.4 SR 3.3.7.5 SR 3.3.7.6 SURVEILLANCE Perform MASTER RELAY CHECK.

Perform SLAVE RELAY TEST.

Perform CHANNEL CALIBRATION.

After re-evaluation,

there are no changes to the current TS page HBRSEP Unit No. 2 3.3-42 CREFS Actuation Instrumentation 3.3.7 FREQUENCY 18 months 18 months 18 months Amendment No. 176

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SR 3.8.4.2 SR 3.8.4.3 SR 3.8.4.4 SR 3.8.4.5 SURVEILLANCE FREQUENCY Verify battery cells, cell plates, and racks show no 18 months visual indication of physical damage or abnormal deterioration that could degrade battery performance.

Remove visible terminal corrosion, verify battery cell to 48-months cell and terminal connections are clean and tight, and

~

r=-"7'"1 24 are coated with anti-corrosion material.

~

Verify each battery charger supplies~ 300 amps at

~ 125 V for~ 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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

1.

The modified performance discharge test in SR 3.8.4.6 may be performed in lieu of the service test in SR 3.8.4.5.

2.

This Surveillance shall not be performed in MODE 1, 2, 3, or4.

Verify battery capacity is adequate to supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

Te-months

~

i.&-months (continued)

HBRSEP Unit No. 2 3.8-20 Amendment No.~

+

U. S. Nuclear Regulatory Commission to Serial: RNP-RA/17-0034 4 Pages (including cover page)

ATTACHMENT 2 RETYPED TECHNICAL SPECIFICATION PAGES

Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS SR 3.3.4.1 SR 3.3.4.2 SR 3.3.4.3 SR 3.3.4.4 SURVEILLANCE FREQUENCY Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

Verify each required control circuit and transfer 18 months switch is capable of performing the intended function.

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

N e utro n detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each required 24 months instrumentation channel.

Perform TADOT of the reactor trip breaker open/closed indication.

18 months HBRSEP Unit No. 2 3.3-34 Amendment No.

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.7.4 Perform MASTER RELAY CHECK.

SR 3.3.7.5 Perform SLAVE RELAY TEST.

SR 3.3.7.6 Perform CHANNEL CALIBRATION.

HBRSEP Unit No. 2 3.3-42 CREFS Actuation Instrumentation 3.3.7 FREQUENCY 18 months 18 months 18 months Amendment No. 176

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SR 3.8.4.2 SR 3.8.4.3 SR 3.8.4.4 SR 3.8.4.5 SURVEILLANCE FREQUENCY Verify battery cells, cell plates, and racks show no 18 months visual indication of physical damage or abnormal deterioration that could degrade battery performance.

Remove visible terminal corrosion, verify battery cell to 24 months cell and terminal connections are clean and tight, and are coated with anti-corrosion material.

Verify each battery charger supplies 2: 300 amps at 2: 125 V for 2: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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

1.

The modified performance discharge test in SR 3.8.4.6 may be performed in lieu of the service test in SR 3.8.4.5.

2.

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify battery capacity is adequate to supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

24 months 24 months (continued)

HBRSEP Unit No. 2 3.8-20 Amendment No.

U.S. Nuclear Regulatory Commission to Serial: RNP-RA/17-0034 5 Pages (including cover page)

ATIACHMENT3 MARKED-UP TECHNICAL SPECIFICATION BASES PAGES

BASES Remote Shutdown System B 3.3.4 SURVEILLANCE SR 3.3.4.2 REQUIREMENTS (continued)

SR 3.3.4.2 verifies each required Remote Shutdown System control circuit and transfer switch performs the intended function. This verification is performed from the remote shutdown panel and locally, as appropriate.

Operation of the equipment from the remote shutdown panel is not necessary. The Surveillance can be satisfied by performance of a continuity check. This will ensure that if the control room becomes inaccessible, the unit can be placed and maintained in MODE 3 from the remote shutdown panel and the local control stations. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. (However, this Surveillance is not required to be performed only during a unit outage.) Operating experience demonstrates that remote shutdown control channels usually pass the Surveillance test when performed at the 18 month Frequency.

REFERENCES HBRSEP Unit No. 2 SR 3.3.4.3 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.

The Frequency of ts months is based upon operating experience and consistency with th pical industry refueling cycle.

SR 3.3.4.4 SR 3.3.4.4 is the performance of a TADOT every 18 months. This test should verify the OPERABILITY of the reactor trip breakers (RTBs) open and closed indication on the remote shutdown panel, by actuating the RTBs. The Frequency is based upon operating experience and consistency with the typical industry refueling outage.

1.

UFSAR, Section 7.4.1.

83.3-113 Revision No. -e-

BASES CREFS Actuation Instrumentation B 3.3.7 SURVEILLANCE SR 3.3.7.1 (continued)

REQUIREMENTS HBRSEP Unit No. 2 The Frequency is based on operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the LCO required channels.

SR 3.3.7.2 A COT is performed once every 92 days on the required radiation monitor channel to ensure the entire channel will perform the intended function.

This test verifies the capability of the instrumentation to provide actuation of both CREFS trains. The setpoint should be left consistent with the unit specific calibration procedure tolerance. The Frequency is based on the known reliability of the monitoring equipment and has been shown to be acceptable through operating experience.

SR 3.3.7.3 SR 3.3.7.3 is the performance of an ACTUATION LOGIC TEST. The train being tested is placed in the test condition. All possible logic combinations, with and without applicable permissives, are tested for each protection function. In addition, the master relay coil is tested for continuity. This verifies that the logic modules are OPERABLE and there is an intact voltage signal path to the master relay coils. This test is performed every 31 days on a STAGGERED TEST BASIS. The Frequency is justified in WCAP-10271-P-A, Supplement 2, Rev. 1 (Ref. 1).

SR 3.3.7.4 SR 3.3.7.4 is the performance of a MASTER RELAY TEST. The MASTER RELAY TEST is the energizing of the master relay. The master relay is actuated by either a manual or automatic initiation of the function being tested. Contact operation is verified either by a continuity check of the circuit containing the master relay or proper operation of the end device during the supported equipment simulated or actual automatic actuation test. This test is performed every 18 After re-evaluation, there are no changes to the current Bases page.

B 3.3-132 (continued)

Revision No. O

BASES CREFS Actuation Instrumentation B 3.3.7 SURVEILLANCE SR 3.3.7.4 (continued)

REQUIREMENTS REFERENCES HBRSEP Unit No. 2 months. The 18 month Frequency is adequate, based on industry operating experience, and is consistent with the typical refueling cycle, which provides the plant conditions necessary for testing.

SR 3.3.7.5 SR 3.3.7.5 is the performance of a SLAVE RELAY TEST. The SLAVE RELAY TEST is the energizing of the slave relays. Contact operation is verified either by a continuity check of the circuit containing the slave relay, or by verification of proper operation of the end device during the supported equipment simulated or actual automatic actuation test. This test is performed every 18 months. The 18 month Frequency is adequate, based on industry operating experience, and is consistent with the typical refueling cycle, which provides the plant conditions necessary for testing.

SR 3.3.7.6 A CHANNEL CALIBRATION is performed every 18 months,....af=-

a~~reMi~ately at every FeR:ieliR9. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.

The Frequency is based on operating experience and is eonsistent witl'I the typieal indt1stry refueling eyele.

1.

WCAP-10271-P-A, Supplement 2, Rev. 1, June 1990.

B 3.3-133 Revision No. ~

ACTIONS 8.1 and 8.2 (continued)

DC Sources - Operating 8 3.8.4 required unit conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.8.4.1 REQUIREMENTS H8RSEP Unit No. 2 Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. The voltage requirements are based on the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery sizing calculations and permit a single battery cell to be jumpered out.

The 7 day Frequency is consistent with manufacturer recommendations and IEEE-450 (Ref. 5).

SR 3.8.4.2 Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

The 18 month frequency is based on engineering judgment and operational experience and is sufficient to detect battery and rack degradation on a long term basis.

SR 3.8.4.3 Visual inspection of intercell, intertier, and terminal connections provide an indication of physical damage or abnormal deterioration that could indicate degraded battery condition. The anticorrosion material is used to help ensure good electrical connections and to reduce terminal deterioration. The visual inspection for corrosion is not intended to require removal of and inspection under each (continued) 8 3.8-42 Revision No. 0

U. S. Nuclear Regulatory Commission to Serial: RNP-RA/17-0034 4 Pages (including cover page)

ATTACHMENT 4 RETYPED TECHNICAL SPECIFICATIONS BASES PAGES

BASES Remote Shutdown System B 3.3.4 SURVEILLANCE SR 3.3.4.2 REQUIREMENTS (continued)

SR 3.3.4.2 verifies each required Remote Shutdown System control circuit and transfer switch performs the intended function. This verification is performed from the remote shutdown panel and locally, as appropriate.

Operation of the equipment from the remote shutdown panel is not necessary. The Surveillance can be satisfied by performance of a continuity check. This will ensure that if the control room becomes inaccessible, the unit can be placed and maintained in MODE 3 from the remote shutdown panel and the local control stations. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. (However, this Surveillance is not required to be performed only during a unit outage.) Operating experience demonstrates that remote shutdown control channels usually pass the Surveillance test when performed at the 18 month Frequency.

REFERENCES HBRSEP Unit No. 2 SR 3.3.4.3 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.

The Frequency of 24 months is based upon operating experience and consistency with the typical industry refueling cycle.

SR 3.3.4.4 SR 3.3.4.4 is the performance of a TADOT every 18 months. This test should verify the OPERABILITY of the reactor trip breakers (RTBs) open and closed indication on the remote shutdown panel, by actuating the RTBs. The Frequency is based upon operating experience and consistency with the typical industry refueling outage.

1.

UFSAR, Section 7.4.1.

B3.3-113 Revision No.

BASES CREFS Actuation Instrumentation B 3.3.7 SURVEILLANCE SR 3.3. 7.1 (continued)

REQUIREMENTS HBRSEP Unit No. 2 The Frequency is based on operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplements fess formal, but more frequent, checks of channels during normal operational use of the displays associated with the LCO required channels.

SR 3.3.7.2 A COT is performed once every 92 days on the required radiation monitor channel to ensure the entire channel will perform the intended function.

This test verifies the capability of the instrumentation to provide actuation of both CREFS trains. The setpoint should be left consistent with the unit specific calibration procedure tolerance. The Frequency is based on the known reliability of the monitoring equipment and has been shown to be acceptable through operating experience.

SR 3.3.7.3 SR 3.3.7.3 is the performance of an ACTUATION LOGIC TEST. The train being tested is placed in the test condition. All possible logic combinations, with and without applicable permissives, are tested for each protection function. In addition, the master relay coil is tested for continuity. This verifies that the logic modules are OPERABLE and there is an intact voltage signal path to the master relay coils. This test is performed every 31 days on a STAGGERED TEST BASIS. The Frequency is justified in WCAP-10271-P-A, Supplement 2, Rev. 1 (Ref. 1).

SR 3.3.7.4 SR 3.3.7.4 is the performance of a MASTER RELAY TEST. The MASTER RELAY TEST is the energizing of the master relay. The master relay is actuated by either a manual or automatic initiation of the function being tested. Contact operation is verified either by a continuity check of the circuit containing the master relay or proper operation of the end device during the supported equipment simulated or actual automatic actuation test. This test is performed every 18 (continued)

B 3.3-132 Revision No. 0

BASES CREFS Actuation Instrumentation B 3.3.7 SURVEILLANCE SR 3.3.7.4 (continued)

REQUIREMENTS REFERENCES HBRSEP Unit No. 2 months. The 18 month Frequency is adequate, based on industry operating experience, and is consistent with the typical refueling cycle, which provides the plant conditions necessary for testing.

SR 3.3.7.5 SR 3.3.7.5 is the performance of a SLAVE RELAY TEST. The SLAVE RELAY TEST is the energizing of the slave relays. Contact operation is verified either by a continuity check of the circuit containing the slave relay, or by verification of proper operation of the end device during the supported equipment simulated or actual automatic actuation test. This test is performed every 18 months. The 18 month Frequency is adequate, based on industry operating experience, and is consistent with the typical refueling cycle, which provides the plant conditions necessary for testing.

SR 3.3.7.6 A CHANNEL CALIBRATION is performed every 18 months. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.

The Frequency is based on operating experience.

1.

WCAP-10271-P-A, Supplement 2, Rev. 1, June 1990.

B3.3-133 Revision No.

ACTIONS 8.1 and 8.2 (continued)

DC Sources - Operating 8 3.8.4 required unit conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.8.4.1 REQUIREMENTS H8RSEP Unit No. 2 Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. The voltage requirements are based on the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery sizing calculations and permit a single battery cell to be jumpered out.

The 7 day Frequency is consistent with manufacturer recommendations and IEEE-450 (Ref. 5).

SR 3.8.4.2 Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

The 18 month frequency is based on engineering judgment and operational experience and is sufficient to detect battery and rack degradation on a long term basis.

SR 3.8.4.3 Visual inspection of intercell, intertier, and terminal connections provide an indication of physical damage or abnormal deterioration that could indicate degraded battery condition. The anticorrosion material is used to help ensure good electrical connections and to reduce terminal deterioration. The visual inspection for corrosion is not intended to require removal of and inspection under each (continued) 8 3.8-42 Revision No. 0

U. S. Nuclear Regulatory Commission to Serial: RNP-RA/17-0034 7 Pages (including cover page)

ATTACHMENT 5 TECHNICAL SPECIFICATIONS AND LICENSE AMENDMENT REQUEST PAGES WITH EDITORIAL CORRECTIONS

ACTIONS (continued)

CONDITION G.

As required by Required G.1 Action E.1 and referenced in Table 3.3.3-1.

SURVEILLANCE REQUIREMENTS REQUIRED ACTION Initiate action in accordance with Specification 5.6.6.

PAM Instrumentation 3.3.3 COMPLETION TIME Immediately

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

SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1; except Functions 9, 22, 23, and 24. SR 3.3.3.3 applies only to Functions 9, 22, 23, and 24.

SR 3.3.3.1 SR 3.3.3.2 SR 3.3.3.3 SURVEILLANCE Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.

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

N eutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

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

Verification of setpoint not required.

Perform TADOT.

HBRSEP Unit No. 2 3.3-31 FREQUENCY 31 days

-t-8-months

~ months

~

Amendment No. r4 t

LOP DG Start Instrumentation 3.3.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Action and associated Completion Time not met.

D.1 Enter applicable Immediately Condition(s) and Required Action(s) for the associated DG made inoperable by LOP DG start instrumentation.

SURVEILLANCE REQUIREMENTS SR 3.3.5.1 SR 3.3.5.2 SURVEILLANCE

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

Verification of setpoint not required.

Perform TADOT.

Perform CHANNEL CALIBRATION with Trip Setpoints as follows:

a.

Loss of voltage Trip Setpoint of 328 V +/- 10%

with a time delay of s1 second (at zero voltage).

b.

Degraded voltage Trip Setpoint of 430 V +/- 4 V with a time delay of 1 O +/- 0.5 seconds.

HBRSEP Unit No. 2 3.3-36 FREQUENCY r@

43-months

~months Amendment No. t.76

SURVEILLANCE REQUIREMENTS continued SR 3.8.1.9 SURVEILLANCE

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

1.

All DG starts may be preceded by an engine prelube period.

2.

This Surveillance shall not be performed in MODE 1, 2, 3, or4.

3.

During periods when a diesel generator is being operated for testing purposes, its protective trips need not be bypassed after the diesel generator has properly assumed the load on its bus.

Verify on an actual or simulated loss of offsite power signal:

a.

De-energization of emergency buses;

b.

Load shedding from emergency buses;

c.

DG auto-starts from standby condition and:

1.

energizes permanently connected loads in s 10 seconds,

2.

energizes auto-connected shutdown loads through automatic load sequencer,

3.

maintains steady state voltage

~ 467 Vand S493 V,

4.

maintains steady state frequency

~ 58.8 Hz ands 61.2 Hz, and

5.

supplies permanently connected and auto-connected shutdown loads for

~ 5 minutes.

HBRSEP Unit No. 2 3.8-7 AC Sources-Operating 3.8.1 FREQUENCY 1-8-months (continued)

Amendment No. ~

SURVEILLANCE REQUIREMENTS continued SR 3.8.1.11 SR 3.8.1.12 SURVEILLANCE Verify each DG's automatic trips are bypassed except engine overs peed.

N 0 TES--------------------------------

1.

Momentary transients outside the load and power factor ranges do not invalidate this test.

2.

This Surveillance shall not be performed in MODE 1or2.

3.

During periods when a diesel generator is being operated for testing purposes, its protective trips need not be bypassed after the diesel generator has properly assumed the load on its bus.

Verify each DG operating at a power factors 0.9 operates for <?: 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

a.

For<?: 1. 75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> loaded <?: 2650 kW and s 2750 kW; and

b.

For the remaining hours of the test loaded

<?: 2400 kW and s 2500 kW.

HBRSEP Unit No. 2 3.8-9 AC Sources-Operating 3.8.1 FREQUENCY 24 months 1'8-months (continued)

Amendment No..z.ea.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.1.15 (continued)

SR 3.8.1.16

5. supplies permanently connected and auto connected emergency loads for <?: 5 minutes.

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

1. This Surveillance shall not be performed in MODE 1or2.
2. SR 3.8.1.16 is not required to be met if 4.160 kV bus 2 and 480 V Emergency Bus 1 power supply is from the start up transformer.

AC Sources-Operating 3.8.1 FREQUENCY Verify automatic transfer capability of the 4.160 kV bus "Ht months 2 and the 480 V Emergency bus 1 loads from the Unit SR 3.8.1.17 auxiliary transformer to the start up transformer.

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

All DG starts may be preceded by an engine prelube period.

Verify when started simultaneously from standby 10 years condition, each DG achieves, in s 10 seconds, voltage

<?: 467 V and frequency<?: 58.8 Hz, and after steady state conditions are reached, maintains voltage <?:

467 V and s 493 V and frequency <?: 58.8 Hz and s 61.2 Hz.

HBRSEP Unit No. 2 3.8-12 Amendment No. +:16-

TS 3.4.1 RCS Pressure. Temperature and Flow DNB Limits SR 3.4.1.4 Verify by precision heat balance that RCS total flow rate is ~ 97.3 x 106 lbm/hr TS 3.4.9 Pressurizer SR 3.4.9.2 Verify capacity of required pressurizer heaters is~ 125KW SR 3.4.9.3 Verify required pressurizer heaters are capable of being powered from an emergency supply TS 3.4.11 Pressurizer PORV SR 3.4.11.2 Perform a complete cycle of each PORV SR 3.4.11.3 Perform a complete cycle of each solenoid air control valve and check valve on the nitrogen accumulators in PORV control system SR 3.4.11.4 Verify accumulators are capable of operating PORVs through a complete cycle TS 3.4.12 L TOP System SR 3.4.12.7 Perform CHANNEL CALIBRATION for each required PORV actuation channel TS 3.4.14 RCS PIVs SR 3.4.14.1 Verify leakage from each RCS PIV is less than or equal to an equivalent of 5 gpm at an RCS pressure <!: 2235 psig, and verify the margin between the results of the previous leak rate test and the 5 gpm limit has not been reduced by ~ 50% for valves with leakage rate > 1.0 gpm SR 3.4.14.2 Verify RHR System interlock prevents the valves from being opened with a simulated or actual RCS pressure signal> 474 psig TS 3.4.15 RCS Leakage Detection Instrumentation SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required containment sump monitor SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor SR 3.4.15.5 Perform CHANNEL CALIBRATION of the required containment fan cooler condensate flow rate monitor TS 3.4.17 eves SR 3.4.17.2 Verify seal injection flow of~ 6 gpm to each RCP from each Makeup Water Pathway from the RWST TS 3.5.2 ECCS - Operating SR 3.5.2.4 Verify each ECCS automatic valve in the flow path that is locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal SR 3.5.2.5 Verify each ECCS pump starts automatically on an actual or simulated actuation signal SR 3.5.2.6 Verify, by visual inspection, the ECCS train containment sump suction inlet is not restricted by debris and the suction inlet trash strainers show no evidence of structural distress or abnormal corrosion TS 3.6.3 Containment Isolation Valves SR 3.6.3.2 Verify each containment isolation manual valve and blind flange that is located outside containment and not locked, sealed or otherwise secured and required to be closed during accident conditions SR 3.6.3.5 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 SR 3.6.3.6 Verify each 42 inch inboard containment purge valve is blocked to restrict the valve from opening> 70 degrees

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