ML18139A160
| ML18139A160 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/02/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8004210010 | |
| Download: ML18139A160 (4) | |
Text
r Docket Nos. 5~
and 50-... 81 Mr. J. H. Ferguson Executive Vice President - Power Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261
Dear Mr. Ferguson:
DISTRIBUTION Docket _Files 50-280 and 50-281.
NRC PDRs (2)
Local PDR TERA NSIC NRR Reading ORB1 Reading D. Eisenhut W. Gammill A. Schwencer D. Neighbors C. Parrish I&E (3)
Attorney, OELD V. Noonan APR O 2 1980 We are continuing our review of containment purging and venting for the Surry Power Station, Units 1 and 2. Your letter dated January 3, 1979 provided us with certain infoi"ination, but we find we need additional information concerning bypass and reset of engineered safety features.
The enclosure lists the information necessary for us to continue our long term review.
Your letter dated February 21, 1980 commits to perform containment venting or purging operations only when the plant is in the cold shutdown or refueling mode until valve operability is justified.
We consider that your commitment meets our interim position as stated in our letter dated October 22, 1979.
Enclosure:
Request fcfr Sincerely, A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors Additional Information cc~ w/enclosure See next page
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- DATE~.. 0/Jf... /.80........ Q4 /... /'J,.Q. -..........................................................................
NRC FORM 318 (9-76) NRCM 0240
-tru.s. GOVERNMENT PRINTING OFFICE: 1979-289-369
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- -':r. J. H. Ferguson Virginia Electric and Power Co~pany cc:
/*1r. Michael \\~. Maupin Hunton and \\*!illia:::s Post Office Box 1535 Richmond, Virginia 23213 Mr. W. L, Stewart, Manager P. o. Box 315 Surry, Virginia 23883 S_wem Li bra ry College of William and Mary Hilliamsburg, Virginia 23185 Donald J. Burke, Resident Inspector Surry Power Station U. s. Nuclear Regulatory Corrrnission Post Office Box 959 Williamsburg, Virginia 23185
ENCLOSURE REQUEST FOR ADDITIONAL INFORKA.TlON FOR BYPASS AND RESET OF ENGINEERED SAFETY FEATURES FOR SURRY UNITS 1 AND 2 DOCKET Nos. 50-280/281 e
- l. The information presented in your FSAR and your letter of January 3, 1979, is not sufficient to determine if the following requirements are met for the safety signals to all Engineered Safety Features (ESF) equipment.
Therefore, identify and justify all exceptions to the following:
Criterion l - In keeping with the requirements of General Design Criteria 55 and 56, the overridinga of one type of safety actuation signal (e.g.,_ radiation) should not cause the blocking of any other type of safety actuation signal (e.g., pressure) for those valves that have no function besides containment isolation.
APR O 2 198G Criterion 2 - Sufficient physical features (e.g., key lock switches)*
are to be provided to facilitate adequate administrative controls.
Criterion 3 - A*system level annunciation of the overridden status should be provided for every safety system impacted when any override is active, (See R.G. 1.47).
Criterion 4 - Diverse signals should be provided to initiate isolation of the containment ventilation system.
Specifically, containment high radiation, safety injection actuation, and containment high pressure (where containrrent high pressure is not a portion of safety injection actuation) should automatically 1nit1ate CVI.
Criterion 5 - The 1nstrumentation and control systems provided to initiate *the ESF shou1d be designed and qualified as safety grade equipment, Criterion 6 - The overriding or resettingb of the ESF actuation signal should not cause any valve or damper to change pos1tion,
- 2.
In addition to responding to the general queation above, please provide the following specific 1nfonnation:
The following definitions are given for clarity of use in this evaluation:
a - Override:
the signal is still present, and it is blocked in order to perform a function contrary to the signal.
b - Reset:
the signal has come and gone, and the circuit is being cleared in order to return it to the normal condition.
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APR O 2 1980
- 2 (1)
Provide an "as built" tabulation of all Engineered Safety Features (ESFj/Auxiliarv Supporting Features (ASF) valves and dampers required to be operated automatically_following an accident.
This tabulation should include the following:
- a.
Component designation
- b.
System served
- c. Safety function (e.g., containment isolation, spray initiation)
- d. Actuation signal sources
- e.
Reference to control circuitry (see 2.(3) below) f.. Indication whether or not the component safety function indicated 1n 2.(1) above can be defeated through the use of a manual override or bypass in either the control system or actuation signal system circuitry.
(2)
For each manual bypass or override feature identified in 2(1) above, provide a description of the physical feature(s) provided to prevent inadvertant operation and to satisfy the requirements of IEEE Std. 279-1971, Section 4.14.
(3)
For each actuation signal system and component actuation system identified in 2fl)d and 2(1)e above, incorporating a manual reset, override or bypass feature, provide a complete circuit description, including detailed pictorial information (1.e., as built circuit diagram, schematics, logics), sufficient to allow a thorough understanding of the operation of such circuitry including the function and effect of all control devices (e.g., relays, contacts, switches, diodes, etc.).
(4)
For each actuat1on signal identified in 2(1) above, identify the design standards, quality assurance requirements, and component qualification standards involved to ensure that the systems will perform their designated safety function upon demand.