ML19224D489
| ML19224D489 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/02/1979 |
| From: | Whitmer C GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907120301 | |
| Download: ML19224D489 (9) | |
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July 2, 1979 3'.
S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C.
20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCil NUCLEAR PLANT UNIT 2 IIPCI AND RCIC SPECIAL TEST PROGRAbi Gentlemen:
Pursuant to 10 CFR 50.90 as required by 10 CFR 50.59 (c) (1), Georgia Power Company hereby proposes an amendment te the Technical Specifications (Appendix A to the Operating License).
The p oposed change would allow the performance of a series of special tests on the HPCI and RCIC systems far Unit 2.
The proposed change would temporarily delete the requirement for the llPCI and RCIC steam line high flow isolation trips to be in effect during each special test.
Attachnent 1 provides a description of the test program, what is expected to be accomplished, and acceptance criteria for the test program.
The high steam line flow isolation instruments protect against steam line breaks.
llowever, high steam line flow is not the only indicator of a steam line break. Low supply pressure and high area air temperatire would also provide inJicatien of a steam line break.
Several instrument s are available which will provide protection in the highly unlikely event of an RCIC or IIPCI steam line break during the test program.
The instruments available for llPCI are a) HPCI equipment room high temperature, b) Surpression pool area high temperature, and c) low steam supply pressure.
The instruments available for RCIC are a) Suppression pool area high temperature, and b) low steam supply pressure.
In addition, personnel stativned at each local panel for RCIC and IIPCI will nc,tify the control room in the event a high Ap condition persists during a test, allowing the operator to isolate the affected system.
The Plant Review Board and Safety Review Board have reviewed the proposed change to the Technical Specification, and have determined that an unreviewed safety question is not involved.
The possibility of a new accideet or mal-fanction not previously considered has not been created because no actual system modliications are involved.
Similarly, the consequences of previously q
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7907120 30./
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Georgia Power ah U. S. Nuclear Regulatory Conmission Office of Nuclear Reactor Regulation Page Two July 2, 1979 analyze 1 accidents or malfunctions are unchanged by the test.
Margins of safety are maintained by the redundant instrumentation..va ilab le to isolate llPCI and RCIC should out of nornal parameters 3e noted.
These margins of safety are strengthened by the stationing of personnel at local panels to advise the operator of high Ap con (itions as noted above.
In order to expedite "he performance of this test prot,m m, we urgently request your earliest review and appron1 of the attached proposed change to the Technical Specifications.
Yours very truly, Q
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f Chas. F. Whitmer RDB/mb Attachment Sworn to and subscribed before me this 2nd day of July, 1979, i
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Ruble A. Thomas George F. Trowbridge, Esquire
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ATTACRMENT 1 SPECIAL HPCI/RCIC TEST PROGRAM I.
EXPECTED ACCOMPLISHMENTS Through the test program described belou, the steady state Ap at steady flow will be determined accurately to enable an accurate setting of the 300% rated flow Ap isolation.
Following corapletion of the series of hot quick starts described below, the accumulated data will be evaluated to determine if a design change will be required for HPCI or RCIC.
If a design change is required as a result of the evaluation, it will be implemented prior to completion of the test program in order to observe the system performance during a cold quick start.
Acceptance criteria for this portion of the cest program are listed below.
II.
TEST PROGRAM DESCRIPTION Validyne DP 15 Ap transducers, or equivalent, will be installed across op flow switches.
The data will be recorded for later analysis during each test.
The Ap isolation switches will be removed from service before each hot quick start and the cold quick start lined up condensate storage tank (CST) to CST.
Hot quick starts will be performed 1 each at 150 psig, 500 psig, and 800 psig reactor pressure, with 3 each at 950 psig, 975 psig and 1000 psig reactor pressure.
In addition, a cold quick start will be performed with each system aligned CST to CST.
Pump discharge pressure for each test will be 100 psig greater than system pressure.
During these quick starts, steady state and peak Ap values will be recorded to enable a determination to be made of the correct value for the high Ap trip setpoint.
The data obtained from these tests will be analyzed to determine the possible need for design changes in the high Ap trip logic, such as the addition of snubbers in the instrument lines or time delay relays. After all instrument adjustments or design modifications deemed necessary have been completed, a cold quick start will be performed for each system with that system injecting into the reactor vessel at a reactor pressure of 975 psig.
The HPCI vessel injection. will be performed at 2; 50%
power anc the RCIC vessel injection wil] be performed at 2; 25% power.
Three additional cold quick starts will be performed CST to CST, with the high Ap isolation trip in service within the succeeding 30 days.
In addition, the Ap instruments on RCIC will be monitored closely to observe for possible problems in pipe geometry or line leakage.
III. ACCEPTANCE CRITERIA The hot quick starts and the initial cold quick start (CST to CST) cre confi;matory tests in nature.
Data vill be collected and evaluated and any necessary actions taken prior to proceeding on with the final series of tests.
For the vessel injection tests and o e succeeding cold quick starts (CST to CST) with the trip logic functioning to be acceptable, each system must start when requited and not isolate due to high steam line Ap d u-qg the start.
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ATTACdMENT 2 NRC DOCFET 50-366 opt ' ATING LICENSE NPF-5 EDWIN I. E TCH NUCLEAR PLANT UNIT 2 PROPOSED CHANCES TO TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the attached proposed amendment to Operating License NPP-5 and have determined that:
a)
The proposed amendment does not require the evaluation of a new Safety Analysis Report or rewrite of the facility license; b)
The proposed amendment does not ccatain several complex issues, does not involve ACRS review, or does not require an environmental impact statement; c)
The proposed amendment does not involve a complex issue, an environ-mentcl issue or more than one safety issue; d)
The proposed amendment does involve a single issue, namely, the temporary removal of the high steam line flow isolation trip for HPCI AND RCIC to allow for a special confirmatory test program; and c)
The propcsed amendment is therefore a Class III amendment.
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ATTACIIMENT 3 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I.11ATCll NUCLEAR PLANT UNIT 2 PROPOSED CIIANCES TO TECHNICAL SPECIFICATIONS The proposed clianges to the Technical Specificatior.=, Appendix A to Operating License NPF-5, uould be incorporated as follows:
INSERT PACE REMOVE PAGE 3/4 3-13 3/4 3-13 3/4 3-14 3/4 3-14 3/4 3-15 3/4 3-15 3/4 3-15a 7
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TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION VALVE GROUPS MINIMUN NUMBER APPLICABLE OPERATED Bi OPERABLE CHANNELS OPERATIONAL 27 TRIP FUNCTION SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION 2:
9 4.
HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION i
HPCI Steam Line Flow - High(d) 3 1
1, 2,. 3 26 c
E3 a.
(2E41-N004 and 2F-N005)
-i
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HPCI Steam Supply Pressure -
Low (2E41-N001 A, B, C, D) 3, 8 2
1,2,3 26 s.
c.
HPCI Turbine Exhaust Diaphragm Pres.ure - High (2E41-N012 A,B,r,D) 3 2
1, 2, 3 26 d.
HPCI Equipmant Room Temperature - High (2E41-N610 A, B) 3 1
1,2,3 26 Suppression Pool Area Ambient e.
Temperature - High (2E51-N603 C, D) 3 1
1,2,3 26 s"
f.
Suppression Pool Area
{'
A Temp. - High (2E51-N6f t C, D) 3 1
1,2,3 25 26 w
Timer Relays (2E41-M60
, 8) 3(i) 1 1'2'3 g.
Suppression Pool Area T.
rature i.
Drywell Pressure-High (2 Ell-N011 C, D) 8 1
1,2,3 26
)
t,s j.
Logic Power Monitor (2E41-Kl)
NA 1
1,2,3 27 D
v;
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION h
VALVE GROUPS MINIMUM NUMBER APPLICABLE GPERATED BY OPERABLE CHANNELS OPERATIONAL o
SIGNAL (a)
PRE TRIP SYSTEM (b)(c)
CONDITION ACTION
[
TRIP FUN E
5.
REACTOR LORE ISOLATION U
~~ TOOLING SYSTEM ISOLATION RCIC Steam Line Flow-Jigb(d) 4 1
1,2,3 26 a.
(2E51-NC17, 2E51 N018) b.
RCIC Steam Supply Pressure -
Lc' (2E51-NC19 A, B, C, D) 4, 9 2
1,2,3 26 c.
RCIC Turbine Exhaust Diaphragm Pressure - High (2E51-N012 A, B, C, D) 4 2
1, 2, 3 26 d.
Emergency Area oooler Temperature -
High (2E51-N602 A, 8) 4 1
1,2,3 26 Suppression Pool Area Ambient e.
Temperature-High (2E51-N603 A, B) 4 1
1,2,3 26 w
i f.
Suppression Pool Area a T-High 4
1 1,2,3 26 (2E51-N604 A, B) g.
Suppression Pool Area Temperature 4(i) 1 1,2,3 26 Timer Relays (2E51-M602 A, B) h.
Drywell Pressure - High g
(2 Ell-N0ll A, B) 9 1
1, 2, 3 26 i.
Logic Power Monitor (2E51-Kl)
NA(h) 1 1,2,3 27 D
6.
SHUTDCWN COI'!_ING SYSTEM ISOLATION Reactor Vessel Water Level-Low 2, 5, 6, 10, 11 2
3, 4, 5 26 a.
(2B21-N017 A, B, C, D) 12 b.
Reactor Steam Dome Pressure-High 11 1
1,2,3 28 (2331-N018 A, B)
TABLE 3.3.2-1(Continued)_
ISOLATION ACTUATION INSTRUMENTATION ACTION ACTION 20 -
Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTbflN within the..llowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 21 Be in at least STARTUP with the main steam line isole. tion valves closed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 22 -
Be in at least STARTUP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
ACTION 23 -
Be in at least STARTUP with the Group 1 isolation valves closed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or in at least HOT SHUTDOWN within 12 1.ours.
ACTION 24 -
Establish SECONDAP,Y CONTAINMENT INTEGP.ITY with the standby gas treatment system operating within one hour.
ACTION 25 -
Isolate the reactor.ater cleanup system.
ACTION 26 -
Close the affected system isolation valves :and declare the affected system inoperable.
ACTION 27 -
Verify power availability to the bus at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or close the affected system isolation valves and declare the affected system inoperable.
ACTION 28 -
Close the shutdown cooling supply and reactor vessel head spray isolation valves unless rea tor steam dome pressure < 135 psig.
NOTES Actuates opeation of the main control room environmental control system in the pressurization mode of operation.
Actuates t1e standby gas treatment system.
When handlir,g irradiated fuel in the secondary containment.
a.
See Specification 3.6.3.1 Table 3.6.3.1-1 for valves in each valve grdJp.
3 b.
A channel may be placed in en inoperable status for up to hours for required surveillance without placing tne trip system in 1 tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
With a design providing only one channel per trip system, an inoperable c.
channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> cr the ACTION required by Table 3.3.2-1 for the Trip Function shall be taken.
d.
Trips the mecharical vacuum pumps.
A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.
e.
b l 0
)'f n HATCH - UNIT 2 3/4 3-15
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION IflSTRUMEilTATION ACTI0tl f.
May be bypassed with reactor steam pressure < 1045 psig and all turbine stop valves closed.
g.
Closes only RWCU outlet isolation valve 2G31-F004.
h.
Alana only.
- i. Adjustable JP to 60 minutes.
- j. Not required for special test program 3/8 3j, HATCH - UNIT 2 3/4 3-15a o