ML19312C380
| ML19312C380 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, McGuire  |
| Issue date: | 05/31/1978 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 7912130907 | |
| Download: ML19312C380 (2) | |
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UNITEo sT ATES t *' "8 4 J's 9 'c, NUCLEAR REGULATORY COMMISSION f
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230 PE AcHTREE STREET, N A sVITE 1217 REGloN 11
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ATLANTA. GEORGIA 30303 k% ~ A r[
EAY 3 21976
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In Reply Refer To:
RII:JPO 50-369, 50-370 50-269,L50-270
- 50-287 Duke Power Co=pany Attn:
Mr. Willia = 0. Parker, Jr.
Vice President, Steam Production P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242
- Gentle =en:
If The ene osed Circular 78-08 is f orwarded to you for information.
there a i any questions related to your understanding of the suggested actions, please contact this office.
Sincerely, James P. O'l i
r Reilly f
Director
Enclosure:
1.
List of IE Circulars Issued in 1978
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'/77
}912130..#+
- s. Duke Power Company cc w/anc1:
J. C. Rogers, Project Manager McGuire Nuclear Station P. O. Box 2178 Charlotte, North Carolina 28242 M. D. McIntosh, Plant Manager McGuire Nuclear Station P. O. Box 488 Cornelius, North Carolina 28031 i
J. E. Smith, Station Manager Oconee Nuclear Station P. O. Box 1175 Seneca, South Carolina 29678 d
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C.
20555 May 31, 1978 IE Circular 78-08 ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUI N 'T AT NUCLEAR POWER PLANTS The NRC staf f initiated a series of actions to confirm the environ = ental qualification of electrical equipment required to perform a safety fune-tion under postulated accident conditions. These actions are sum =arized in the Cec =ission's April 13, 1978 Order in response to a petition from the Union of Concerned Scientists.
Information sbtained fro = recent licensee equipment tests and evaluations have ir dicated potential problems in qualification of installed equipment.
As a result, the NRC expanded these actions to include an environmental review of safety-related electrical equipment at selected older plants.1 This review did not identify generic quclification deficiencies.
However, as a result of IE Bulletins and the aforementioned testing to confirm qualification, specific deficiencies were identified.
Poor installation practices, inadequate consideration of subcomponents and omission of certain environmental parameters in the design are examples of such deficiences.
In addition, the documentation of qualification was found to be inadequate in maay cases and the initial response to some licensees indicated a lack of detailed knowledge of the quality of installed equipment.
The purpose of this Circular is to bring to your attention such deficienciet; and to highlight the important lessons learned.
In its April 13, 1978 Order, the Com=ission indicated that "In order to fulfill its regulatory obligations, NRC is dependent upon all of its licensees for accurate and timely information.
Since licensees are directly in control of plant design, construc-tion, operation and maintenance, they are the first line of defense to ensure the safety of the public.
NRC's role is one primarily of review and audit of licensee activities, recognizing that limited resources preclude 100 percent inspection.
Furthermore, the Commission notes that some of the licensee's initial responses indicate a lack on their part of detailed know-ledge of the quality of installed plar* equipment.
Licensees must have this detailed understanding c2 their own plants in order to meet their obligations for public safety by ensuring a 1 of 3 0,AAd}
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IE Circular 76-08 May 31, 1976 sound basis for making assessmentt of plant safety. The NRC establishes general safety criteria, sets specific requirements for many aspects of reactor design and operation, and ensures compliance with these criteria and requirements by independent audit.
While, in the Commission's view, these activities play a vital role in ensuring safe plant open
- ion, they are not a substitute for licensee safety reviews.
The licensees must be knowledgeable and vigilent and must take more initiative in f erreting out details of potential plant weaknesses."
As part of this obligation, you should examine installed safety-related electrical equipment, and ensure appropriate documentation of its qualification to function under postulated accident conditions.
Specific guidance on the subject of environmental qualification can be found in IEEE 323-1971 and 1974, as augmented by Regulatory Guide 1.89.
Examples of specific defici.ncies identified in information provided by licensees are as follows:
1.
Connectors: Responses to IE Bulletins 77-05 and 77-05A revealed in certain instances a lack of qualification data for environmental parameters and inadequate design of connectors for postulated
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accident conditions. 2 2.
Penetrations: A failed penetration prompted issuance of IE Bulletin 77-06.
Responses to this bulletin showed adequate documentation for the qualification of the penetration assembly was not readily available in some cases.2 In one instance, the electrical connections of the penetrations were not qualified in conjunction with the penetration assembly,3 which demonstrates a lack of consideration for qualification of interfacing components.
3.
Terminal blocks: Because of unprotected terminal blocks in penetration areas inside containment of Haddam Neck,Bulletin 78-02 was issued. These unprotected blocks were replaced with blocks designed to function in the LOCA and main steam line break environments.4 Responses to the Bulletin revealed two other facilities, Yankee Rowe and Ginna, with such unprotected blocks.5,6 Other terminal blocks were found to be inadequately qualified due to poor design or installation practices, even though they were in enclosures.7,8,9 and 10 2 of 3
7 Circular No. 7E-05
..ay 31, 1976 LISTING OF IE CIRCULARS ISSUED IN 1978 Circular Subject Date Issued To No.
of Issue 78-01 Loss of Well Logging 4/5/78 All Holders of Source Well Logging Source Licenses 78-02 Proper Lubricating Oil 4/20/78 All Holders of for Terry Turbines Reactor OLs or cps 78-03 Packaging Greater Than 5/12/78 All Holders of Type A Quantities of Reactor OLs, cps, Few Specific Activity Fuel Cycle, Radioactive Material Priority I Material for Transport and Waste Disposal Licenses 78-04 Installation Errors that 5/15/78 All Holders of Could Prevent Closing of Reactor OLs or Fire Doors cps 78-05 Inadvertent safety 5/23/78 All Holders of Injection During Reactor OLs or Cooldown cps 78-06 Potential Common Mode 5/25/78 All Holders of Flooding of ECCS Equip-Reactor OLs or ment Rooms at BWR cps Facilities 78-07 Damaged Components 5/31/78 All Holders of On a Bergen-Paterson Reactor OLs or Series 25000 Hydraulic cps Test Stand Encloscre Page 1 cf 1
1.
"Short Term Safety Assesc,ent on the Environmental Qualifications of Safety-Related Electrical Equipment of SEP Operating Reactors,"
May 1978, enclosure to staff memorandum to Commission, dated May 12, 1978 and issued as NUREG Report 0458.
2.
"NRC Staf f Report on Union of Concerned Scientists' Petition for Emergency and Remedial Action," December 15, 1977, enclosure to staff memorandum to Commission, dated December 15, 1977.
3.
Letter from Consumers Power Company to NRC dated April 6, 1978, including, " Summary of Qualifications of Electrical Penetration Ass.umbly Connectors for the Palisades Plant," Docket No. 50-255.
4.
NRC Su==ary of January 29, 1978 meeting on " Environmental Qualifica-tion of Terminal Blocks and Replacement of Terminal Blocks, Hadda=
Neck Plant," Docket No. 50-213, dated January 30, 1978.
5.
NRC Sum =ary of February 1,1978 meeting, Yankee Rowe Nuclear Power Station (terminal blocks), Docket No. 50-29, dated February 3,1978.
NRC Suc=ary of February 1, 1978 meeting on " Environmental Qualifica-6.
tion of Terminal Blocks and Replacement of Terminal Blocks," R. E.
Ginna Nuclear Plant, Docket No. 50-244 dated February 2, 1978.
7.
Letter from Connecticut Yankee Atomic Power Company to NRC, dated including "Haddam Neck Plant Summary of Environ-March 29, 1978, mental Qualification Test Program, Terminal Block / Box Combinations,"
Docket No. 50-213.
8.
Letter from Consumers Power Company to NRC, dated April 12, 1978, including information on terminal blocks at Palisades, Docket No.
50-255.
Letter from Indiana & Michigan Power Company to NRC, dated March 22, 9.
1978 regarding terminal blocks at D. C. Cook Unit No. 2, Docket No.
50-316.
- 10. Letter f rom Indiana & Michigan Power Company to NRC, dated April 21, 1978, regarding terminations at D. C. Cook Unit Nos. I and 2, Docket Nos. 50-315 and 50-316.
- 11. Staf f memorandum, " Status of Monticello Electrical Splice Upgrade,"
dated May 10, 1978, Docket No. 50-263.
- 12. Letter from Consumers Power Company to NRC, " Environmental Qualifica-
13.
Letter from Consumers Power Company to NRC, " Environmental Qualifica-tion for Palisades," dated February 24, 1978, Docket No. 50-255.
14.
Letter from Westinghouse to E. G. Case, dated April 26, 1978, regarding environmental qualification status for D. C. Cook Unit 2, Docket No. 50-316.
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Table 4.1-2 MINIMUM EQUIPMENT TEST TREQUENCY_
T'est Fliquency Item
.Bi-Weekly Control Rod Movement ( )
Movement of Each Rod 1.
Setpoint '
50% Annually 2.
Pressurizer Safety Valves 25% Annually Setpoint 3.
Main Steam Safety Valves Prior to Functional Refueling System Interlocks Refueling 4.
Monthly Main Steam Stop Valves (1}
Movement of Each Stop 5.
Valve Dtily Evaluate 6.
Reactor Coolant System Leakage Annually Functional 7.
Condenser Cooling Water System Gravity Flgd Test Monthly Functional 8.
High Pressure Service Water Pumps and Power Supplies Prior to Functional Refueling 9.
Spent Fuel Cooling System Annually-Visual Inspection 10.
Hydraulic Snubbers on Safety-Related Systems Monthly and Prior High Pressure and Low ( )
Vent Pump Casings to Testing 11.
Pressure Injection System Once Per Fuel Validate Flow to be 12.
Reactor Coclant System Flow Cycle at least:
Unit 1 141.30 x 10 lb/hr l
Unit i 143.8 x 10 lb/hr Unit 3 141.30 x 10 lb/hr Applicable only when the reactor is critictl (1)
Applicable c.tly when the reactor coolant is above 200 F and at a (2) state temperature and pressure.
(3)
Operating pumps excluded.
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4.1-9Amendments 45, 45 & 42 10l::/7;-
T a
2400 2200 a
G 5
0 E
2000 3
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E 1
/ 2 b
S O"
1600 1600 I
I 560 580 600 620 640 Reactor Coolant Outlet Temperature F
RIA0 TOR COOLANT FLOW PUMPS OPERATING CURVE (GPW1 POWER (TYPE OF LIMIT) 1 374880 (1005) 112$
Four Pump (DNBR Limite:)
2 280035 (74.7%)
36.7%
inree Pumo (JNBR Limite:)
3 183690 (495) 59 0',
One Pumo in Eacn Laag (Quality Limite3) i i
CORE PROTECTION SAFETY LIM VNIT 2 I
OCONEE NUCLEA.R STATION 2.1-11 Figure 2.1-3B Amendments 45. 45 & 42
l'ahle 2.3-1B Unit 2 Reactor Protective System Trip Setting f.laitts lwo Heactor thic React or four Reactor Three Reactor Coolant Pumps Coolant Pump Coulant Pumps Coolant ruinps Open at ing in A Opes.it ing in OpesatIng Operating Single tuop
(:..c le loop (Opes at ing l'oues (Operating Power (Oper.atlug Powes (Operating Shut down RPS Seggtnt
-100% H_ated L _
-75% lt er ed)
-46% Nated)
-492 kated)_
Byp.es s 1.
Nuclear Power m m.
105.5 105.5 105.5 105.5 5.0
(% Rated) 2.
Nuclear Power mx. Based 1.055 t s.nes t Inw 1.055 imes tlow 0.9W t ime Ilaw 1.055 tame, flow Bypassed on fluw (2) and Inibalance, minus reduction urinus reduct ion minus reduct ion minus rc.luction
(% Rated) due to tabalance
.lue to imbalance d ue t o imt.a l aisc e due to in.balanc e 3.
Nuclear Power Nx. Based NA NA 55% (5) (6) 551 Bypassed on Puop Monitors. (% Rated) 4.
tilgh
- ir. or Coolant 2355 2355 2155 2355 1720 System Pressure, psig, Ham.
5.
lev Reactor Coolant 1800 1H00 1800 1800 Bypassed System Picssure, psig. Min.
6.
Variable 1.ow Reactor (11.14 T
- 4 /06)
( 11.14 T
- 4 706) III (11.14 T 4706)III (11.14 T 4706)III Bypassed F
Costant System Pressure
{
pstr,, Min.
7.
Reactor Coolant Temp.
. 619 619 619 (6) 619 619 eo v., n..
y
)
Q 8.
Hip,h Itcactor n at td tng 4
4 4
4 4
Pressure, psig, H.ex.
M (1) T is lu deBrees Fahrenheit ( F).
(5) l'eartur power level toip set point produced
- "E by pump contact sanil t o r reset to 55.01.
A (2) Reactor Coolant hystem Flow, Z.
(6) Specilicat ion 1.E.81 applies. Trip one of the two prot ec t ion channels acceiving outlet (3) Administ rat ively cont rolled reduct ion set temperature inf ormation t rum sensors in the m
only during reactor shutdown.
idle loop.
(4) Autonitically set when other segment s of C
the itPS are bypassed.
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, Conclusion, We have concluded, based on the considerations discussed above, that:
(1) because the amendtr. ants do not involve a sigaificant increase in the probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Date:
July 29, 1977 l
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