ML19262A959
| ML19262A959 | |
| Person / Time | |
|---|---|
| Issue date: | 10/11/1979 |
| From: | Triplett M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19262A953 | List: |
| References | |
| CON-FIN-A-6256 20-80-39, NUDOCS 7912110357 | |
| Download: ML19262A959 (11) | |
Text
.
t-NRC Fomu 173 u s nucle Am PEGuLAf ony couusssioN omot a muusE R in.7:n 20-80-39 STANDARD ORDER FOR DOE WORK Octcber 11, 1979 IM UED 70; IDOE Offeel 885UED BY. (NRC Of fcel ACCOUNTl86G CITATION APPmOpmeATION Su 906 Idaho Operations Office Office of Nuclear Reacter 31X0200.200 Regulation PERFORMING ORGANIZATION AND LOCA'lON 20-19-01-03 EG&G Idaho Falls na au==a A6256 7"NK PERIOD THis ORDER I
FIN TITLE FlxED O
'ESTiuATEo G Electrical, Instrumentation & Control Systems Support Fl071/79 Y/30/80 OBLIGATION AVAILABILITY PROVIDED BY:
A.
THl3 ORDER S
.g
- e. TOTAL OF ORDERS PL ACEO PRIOR TO THis O ATE WsTOHJ PERFORMING ORG ANIZATION UNDE R THE SAME "APPROPR1 ATIOf! SYMBOL" AND THE FIRST FOUR DIGITS OF THE 3
- 1B&R NUMef R ' CITE D A80V(
CdO OOn C. TOTAL ORDERS TO DATE NOTAL A 4 81 860,000 0 AMOUNT INCLUDED IN "C" APPLICABLE TO THE " FIN NUM8E R" CITED IN THis OR09R.
S,20,000 FINANCI AL FLEX 181LITY.
@ FUNDS WILL NOT BE REPROGRAMMED BETWEEN FINS. LINE O CONSTITUTES 4 L,MITATION ON OBLIGATIONS
'AUTHORIZiD.
O FUNDS MAY BE REPROGR AMMED NOT TO EXCEED ? 10% OF FIN LEVEL UP TO St M. LINE C CONSTIT ON OBLIGATIONS AUTHORIZED-STANDARD TERMS AND CONDITIONS PROVIDED DOE ARE CONSIDERED PART OF THIS ORDER UNLESS OTHERWISE NOTEO.
ATTACH ME NTS.
THE FOLLOWING ATTACHMENTS ARE HERE8Y SECURITY:
MADE A PART OF THl3 ORDER:
C WORK ON THl3 ORDER 15 NOT CLASSIFIED.
O STATEMENT OF WOR K O WORK ON THis ORDER thv0LVES CLASSIFIED O ADDITIONAL TERMS AND CONDITIONS INFORMATION. NRC FOA*/18715 ATTACHED.
O OTHER REMARKS 3
After signature, please send a copy of this order u M. Paulette Triplett, NRR, P-428.
1528 225 ISSUING AUTHORITY ACCEPTING ORGANIZATION SaGNatumhaulette Triplett$ Rd<cf Ijf}MSi j
NATum:
M.
Fiscal Assistant ll[/ 3./ 7 NRC FORM 173 I2-78)
C A TE 7912110
l SCOPE OF WORK i
Electrical, Instrumentation and Control Systems Support Select EI&C Issues General The review of selected EI&C issues is intended to establish:
(1) the adequacy of engineered safety feature actuation signal circuitry of i
containment purge isolation valves, (2) whether the BWR reactor protec-tion system can accommodate the effects of sustained abnomal voltage
'l and frequency conditions from non-class lE power supplies, (3) the adequacy of degraded grid voltage detection capability and proposed licensee modifications, (4) compliance with IE Bulletin 79-01 which addresses qualification of safety related electrical equipment, (5) selected other safety reviews from existing and ongoing TACS; and (6) on-call technical assistance.
1528 226
Task 1.
CONTAINMENT PURGE i
Background
A recent abnormal occurrence report detailed the inadvertent manual I
bypassing of the automatic safety injection actuation signal. The i
bypass would have blocked the automatic safety actuation signals l
to the containment purge isolation valves during a postulated LOCA.
The NRC is reviewing the circuitry of all ESF actuation signals which have override capability on all licensed power reactors.
STATEMENT OF WORK EG&G shall provide technical assistance in reviewing the ESF actuation signals at selected plants. The criteria for the review are based upon IEEE Std. 279-1971 and the NRC generic letter sent to all licensees dated November EC,1978.
EG&G shall provide written technical evaluations as to whether the plants listed below meet the criteria:
Arkansas 1/2 Brunswick 1/2 Cook 1/2 FitzPatrick Hatch 1/2 Millstone 2 Oconee 1/2/3 Salem 1 Three Mile Island 1/2 1528 227
Task 2.
RPS POWER SUPPLY L
l
Background
During the review of the Hatch 2 operating license application, NRC questioned the capability of the Class lE reactor protection system (and other Class lE systems and components powered from the RPS power supply) to accorrrnodate the effects of possible sustained g
abnormal voltage and frequency conditions from the non-Class lE power supply. These abnormal power conditions could be caused either by combinations of undetected single failures or by multiple failures caused by earthquakes. These abnomal power concitions could result in damage to the Class lE systems and components with the attendant potential loss of capability to perform their intended safety function. NRC has determined that all BWR's may be vulnerable to the same potential failures on Hatch 2.
GE has proposed a design in conceptual fom which will resolve NRC's concerns. The proposed modifications consist of the addition of two Class lE " protective packages" in series between each motor-generator set and its respective reactor protaction system (RPS) bus, and the addition of two similar packages in series between the alternate power source and the RPS busses.
Each protective package would include a breaker and astociated overvoltage, undervoltage and underfrequency relaying. Each protective package would be +estable and seismically qualifi as Class lE equipment. Some facilities may adopt the GE design; others are preposing plant-specific modifications.
1528 228
l I Statement of Work EG&G shall review the submittals of the licensee which request installation of the protective packages to make sure that they i
i meet the NRC criteria. EG&G shall provide written technical evluations to NRC.
1528 229
Tas k 3.
DEGRADED GRIO VOLTAGE i
I
Background
At present, all nuclear power plants detect the presence or absence of power on the power grid serving the station. The trip point for the sensor is typically quite low, perhaps 50% of nominal, i
There is a possibility that, under unusual circumstances, the grid voltage may drop below the range for which the equipment was designed, yet not low enough to trip the loss-of-power sensor.
Continued operation under such degraded grid voltage conditions may damage equipment. The NRC has requested licensees to design a protection system which will detect a corbination of both sustained and lower than adequate voltage on the power grid and switch the station auxiliary equipment to backup source (s). In addition, the NRC has requested the licensees review the power distribution network within the plant to make sunt that the network can supply the correct voltage under all normal and abnormal conditions.
Statement of Work part A EG&G shall provide technical assistance in reviewing the proposed circuitry for degraded grid voltage detection and propose" licensee modifications. The criteria for the review are IEEE-279 and NRC staff positions.
EG&G will provide written technical evaluations as to whether the plants meet the NRC criteria.
152B 230
Evaluations will be performed on the following plants:
Beaver Valley Indian Point 2 Big Rock Point 1 Indian Point 3 Browns Ferry 1 Kewaunee 1 Browns Ferry 2 Lacrosse Browns Ferry 3 Maine Yankee Brunswick 1 Monticello Brunswick 2 Oyster Creek D. C. Cook 1 Palisades Dresden 1 Quad Cities 1 Dresden 2 Quad Cities 2 Dresden 3 Zion 1 James A. Fitzpatrick Zion 2 Hatti1 1 Three Mile Island 1 Crystal River 3 Part B EG&G will review the analysis of the plant's distribution system to be sure that it meets the applicable criteria.
1528 231
Evaluations will be perfonned on the following plants:
Indian Point 2 Beaver Valley 1 Indian Point 3 Big Rock Point i Kewaunee 1 Browns Ferry 1 Lacrosse Browns Ferry 2 Maine Yankee Browns Ferry 3 Monticello Brunswick 1 Oyster Creek Brunswick 2 Palisades D. C. Cook 1 Quad Cities 1 Dmsden 1 Quad Cities 2 Dresden 2 Zion 1 Dresden 3 Zica 2 Jarnes A. Fitzpatrick Three Mile Island 1 Hatch 1 Crystal River 3 1528 732
Task 4.
EQUIPMENT QUALIFICATION
1 Background
On February 8,1979, the NRC Office of Inspection and Enforcement i
issued IE Bulletin 79-01; entitled, " Environmental Qualification of Class lE Equipment." This bulletin requested that licensees for operating power reactors complete within 120 days their reviews of equipment qualification begun earlier in connection with IE Circular 78-08.
The objective of IE Circular 78-08 was to determine whether proper documentation existed to verify that all Class' lE electrical equipment would function as required in the hostile environment which could result from design basis events.
Statement of Work EG&G shall provide technical assistance in reviewing the quali-fication of the safety related equipment. EG&G shall provide technical evaluations as to whether or not the equipment has been shown to be qualified for the postulated service conditions.
These evaluations will be based on specific guidelines and acceptance criteria provided by the NRC.
1528 2M
g Task 5.
ON CALL ASSISTANCE
Background
Historically, NRC has requested some technical assistance on licensing actions (and other topics) which cannot be specified at the beginning of the year.
Tasking EG&G will perfonn tasking as mutually r. greed to with NRC.
1528 2M
MILESTONE CHART EICS SUPPORT FY 1980 JAN 1 APR 1 JULY l OCT -1 Tasi; 1 - CONTAINMENT PURGE A
A.
Meetings or Questions B.
EG&G Final TER's h
Task 2 - RPS POWER SUPPLY A
A.
Review Licensee Submittals B.
EG&G Final TER's A
Task 3 - DEGRADED GRID VOLTAGE A.
Part ' A' EG&G Final TER's h
B.
Part 'B' EG&G Final TER's A
Task 4 - EQUIPMENT QUALIFICATION
-A.
EG&G Final TER's A
Task 5 - ON CALL ASSISTANCE A
1528 235
,