ML20235H961
| ML20235H961 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/07/1987 |
| From: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| To: | Capra R Office of Nuclear Reactor Regulation |
| References | |
| GL-87-06, GL-87-6, NUDOCS 8707150333 | |
| Download: ML20235H961 (4) | |
Text
.. __ _ - _ - -
c
.' s B ALTIMORE -
GAS AND ELECTRIC '
CHARLES CENTER R O. BOX 1475 BALTIMORE, MARYLAND 21203 JOSEPH A.TIERN AN Vict PntsIDENT NucLcAn ENERGY l
l l
July 7,1987 -
1 U. S. Nuclear Regulatory Commission Washington, DC 20555 i
ATTENTION:
Mr. - R. A. Capra, Director
' Directorate I-l Division of Reactor Projects - I/II
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Response to Generic Letter 87-06, " Periodic Verification of Leak Tinht Integrity of Pressure Isolation Valves"
REFERENCES:
(a) Generic Letter 87-06, '" Periodic Verification of~ Leak Tight Integrity of Pressure Isolation Valves," dated March 13, 1987 (b) Letter from Mr. J. A. Tiernan (BG&E), to Document Control Desk (NRC), dated February.26, 1987, inservice Test Program for Safety-Related Pumps and Valves (c) ASME Boiler and Pressure Vessel Code,Section XI,1983 Edition through the Summer 1983 Addenda Gentlemen:
In Generic Letter 87-06 (Reference a), you requested, pursuant ~ to 10 CFR 50.54(f),
that we submit a list of all Reactor Coolant System pressure isolation valves as well-as a description of the periodic tests performed on these valves. Our response to Generic Letter 87-06 is provided as an Attachment.
8707150333 870707 PDR ADOCK 05000317 P
PDR o
L--____--_--_________-___-_
__-____L-_
__--_-_-__a
Mr.'R. A. Capra i
July 7,1987
.j
~ Page 2 i
. Should you have any questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, M
STATEOFMARYLAND :
]
TO WIT:
COUNTYOFCALVERT :
Joseph A. Tiernan, being duly sworn states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides -
the foregoing response for the purposes therein set forth; that the. statements made are true and correct to.the best of his knowledge, information, and belief; and that l
he was authorized to provide the response on behalf of said Corporation.
h WITNESS my Hand and Notarial Seal:
Notary Public g
/, /99d My Commission Expires:
I/
d Date :
JAT/LSL/ dim Attachment cc:
D. A. Brune, Esquire J. E.
Silberg, Esquire S. A.McNeil,NRC W. T. Russell, NRC T. Foley/D. C. Trimble, NRC
_-----,---------_~~-._--__--_--._--.-------x-
- - - - ~
ea ATTACIIMENT
]
I CALVERT CLIFFS RESPONSE TO GENERIC LETTER 87-06 The following responds to your request for information regarding pressure isolation valves (PIVs). Pressure isolation valves are defined for each interface as any two valves (normally shut during power operation) in series, within the Reactor Coolant Pressure Boundary (as described in 10 CFR 50.2), which separate the high pressure Reactor Coolant System (RCS) from an attached low pressure system. The purpose of the PlVs is to reduce the possibility of inter-system leakage which would pressurize attached low pressure systems to pressures exceeding their design limits. In Generic Letter 87-06, you asked that we provide:
o A list of all PlVs, o A description of the periodic tests or other measures performed, to assure the integrity of the valve as an independent barrier at the Reactor Coolant Pressure Boundary, o The acceptance criteria for each PIV's leakage, if any, o The operational limits for each PIV, if any, and o The frequency of each periodic test.
This information is provided below by system and is a summary of our 10-year ASME J
Section XI Pump and Valve Test Program submittal (Reference b). These valves and their associated periodic tests and requirements are similar fm both Units I and 2.
Safety Iniection System o
Safety I'liection Tank Outlet Check Valves (SI-215. 225. 235. 245)
These valves are leak rate tested in accordance with IWV-3420 of Reference (c) at least once a refueling interval. The acceptance criteria for leakage is s 3 gpm for any safety injection loop and s 6 gpm total leakage for all four loops.
i o
High Pressure Safety injection and Low Pressure Safety Injection Combined Header Check Valves (SI-il8.128.138.148)
The leakage across these check valves is quantified by measuring the pressure increase upstream of the check valve while applying pressure to the check valve in the reverse flow direction. The acceptance criteria is < 100 psig increase over a three-minute period. This test is performed at least once a refueling interval. These check valves are exercised in accordance with IWV-3520 of Reference (c) whenever the plant achieves a MODE 5 condition (COLD SHUTDOWN). _ _ _ _ - _ _ _ _ _ _ _
.i,a ATTACTIMENT CALVERT CLIFFS RESPONSE TO GENERIC LETTER 87-06 o
Safety Iniection Looo Isolation Check Valves (SI-217. 227. 237. 247)
)
The pressure upstream of these valves is continuously monitored by remote 1
indication in the control room. Sig,nificant leakage past these valves ' would l
result in an alarm. The Calvert Cliffs alarm manual requires the operator to take positive measures to assess check valve leakage. follo. wing receipt of the alarm. This continuous monitoring provides assurance that these valves are meeting their pressure isolation function.
o Shutdown Cooling Return Header Isolation Motor-Ocerated Valves (MOV-651. 652)
These valves are local leak' rate tested in accordance with 10 CFR 50 Appen-l i
dix J requirements every refueling outage. The acceptance criteria for the specific surveillance test for these valves is s 40,000 secm. The overall integrated leakage rate Limiting Condition for Operation (LCO) for all con-I tainment penetrations and valves is < 0.60 La (207,600 secm) where La (Maximum Allowable Leakage Rate) is 346,000 secm. These valves are also stroke tested in accordance with IWV-3410 of Reference (c) whenever the plant ' achieves a MODE 5 condition (Cold Shutdown), however, not more frequently than every three months.
i Reactor Coolant and Water Process Samole System / Post Accident Samole Systfm o
Combined Samole Outside Containment Isolation Valve (CV-5464)
This valve is local leak rate tested in accordance with 10 CFR 50 Appendix J requirements each refueling outage. The acceptance criteria for the surveil-lance test for this valve is $2,000 secm. The overall integrated leakage rate LCO for all containment penetrations and valves is < 0.60 La. (207,600 secm) where La is 346,000 secm. This valve is stroke tested quarterly in accordance with IWV-3410 of Reference (c).
o Pressurizer Vaoor Samole Isolation Valve (CV-5465)
Same as CV-5464.
o Pressurizer Liould Samole Isolation Valve (CV-5466)
Same as CV-5464.
o Hot Lee Samole Isolation Valve (CV-5467)
Same as CV-5464.
NOTE: CV-5465, 5466, and 5467 are in parallel with one another and in series with CV-5464.