ML20100J100
| ML20100J100 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/05/1984 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-84-130, NUDOCS 8412100215 | |
| Download: ML20100J100 (4) | |
Text
N SNUPPS Stenderdized Nuclear Unit Power Plant System a choke cherry Reed Nicholas A. Petrick Rockville, Meryland 20850 Executive Director mo sse December 5, 1984 SLNRC 84- 0130 FILE: 0541 SUBJ:
ECCS Check Valve Testing Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No.: STN 50-482
Dear Mr. Denton:
In a meeting between Kansas Gas & Electric Co. (KGE), Office of Nuclear Reactor Regulation (NRR), and Region IV personnel on November 28, 1984, KGE described the Wolf Creek preoperational test results concerning the check valves which form the high pressure to low pressure isolation barrier between the reactor coolant system and the lower pressure ECCS systems.
Test results for many of these check valves did not meet the acceptance criteria given in FSAR Section 14.2.12.1.38.
KGE committed in the meeting to document and submit for NRC approval the proposed resolution of this issue.
KGE has concluded that inappropriate test acceptance criteria were applied during the preoperational test.
The applied acceptance criteria are based upon the architect engineer's specifications for valve pur-chase; a very stringent (i.e., small), cold, bench-test leakage rate was specified. The appropriate leakage criteria (attached) for in plant testing are those specified by the final draft of the Wolf Creek Tech-nical Specification on reactor coolant system operational leakage (Section 3.4.6.2.f).
Further, cold testing at pressure is accept-able per the Technical Specifications.
The attached FSAR page has been revised to' reflect this conclusion plus eliminate an unnecessary test prerequisite.
NRR review and approval of this change is requested.
Very truly yours, Nic olas A. Petrick SLA/nld7al5 Attachment cc: See Page 2 hgg2gDO OO A
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- s-4 b
' SLNRC 84- 0130-
-Page 2.
4 cc:
G.-L. Koester KGE J. M. - Ev ans.
KCPL-D. F.'Schnell UE.
J. Neisler/B. Little USNRC/ CAL H. Bundy.
USNRC/WC l.
W. L.~Forney-USNRC/RIII D. R. Hunter.
USNRC/RIV 4
A8ac4most to f4dd-Bf. 0130 FINAN! DWFWF REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 gpm UNIDENTIFIED LEAKAGE, 1 gpa total reactor-to-secondary leakage through all steam c.
generators not isolated from the Reactor Coolant System and 500 gallons per day through any one steam generator, d.
10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, 8 gpm per RC pump CONTROLLED LEAKAGE at a Reactor Coolant System e.
pressure of 2235 t 20 psig, and f.
1 gpm leakage at a Reactor Coolant System pressure of 2235 t 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.*
APPLICABILITY:
MODES 1, 2, 3, and 4.
i ACTION:
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STAND 8Y a.
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage fron l
Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
With any Reactor Coolant System Pressure Isolation Valve leakage c.
greater than the above limit, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or be in at least HOT STANDBY within the i
next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with i
an RCS pressure of less than 600 psig.
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- Test pressures less than 2235 psig but greater than 150 psig are allowed.
Observed leakage shall be adjusted for the natural test pressure up to 2235 psig assuming the leakage to be directly proportional to pressure differential to the one-half power.
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WOLF CREEK - UNIT 1 3/4 4-19
r&bm.h ka SLNCC 8Y 0130 SNUPPS 14.2.12.1.38 Safety Injection Check Valve Test (S-03EM03) 14.2.12.1.38.1 Objectives To demonstrate the integrity of accumulator outlet line and loop safety injection line check valves and backup check valves by performing backleakage tests. The operability of the various safety injection line check valves under their design q : : ting conditions is also verified. l 7res.s ot-e. 14.2.12.1.38.2 Prerequisites a. Required component testing and instrument calibration are complete. b. Required electrical power supplies' and control circuits are operational. \\ \\ sok % % o % k e k i % k n % o % k a M 1 % h g [ The reactor coolant system is at normal operating W p a r a pressure, hqi At%hWbagb4;g%1WQ k n r r 14.2.12.1.38.3 Test Method a. Check valve leak testing is performed with the reactor / p coolant system at normal operating J rpffe/6)rt' r%#'ptff' [ pressure. b. Check valve operability is performed gpd'ryf'gg[dp6 t" ) f f/cyff h/t fuWlosfay'Jrtb(tM by verifying flow through I the check valves at reduced reactor coolant pressure. 14.2.12.1.38.4 Acceptance Criteria l limits f Che k valve eakage rates are within f6fpfp'$ a. es51,Lt p Tak.eJ 5,ut/;uk;, Seda 3.y.c,z i b. Injection line check valve operability is demonstrated by verification of flow through the check valves in each of the safety injection lines to the reactor coolant system. I 14.2-57}}