ML19249E535
| ML19249E535 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/15/1978 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19249E534 | List: |
| References | |
| NUDOCS 7910010650 | |
| Download: ML19249E535 (9) | |
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ICSB READIt1G Docket tlos. 50-416 (b>+'b Yk 50-417 I'.E!:0PRIDO:1~ FOR:
J. Stolz, Chief, Light Uater reactors Granch' 1, CPil FF. Cal:
T. A. Ippolito, Chief, Instrumntation liid Control Systems Branch, DSS 7'
SU3 JECT:
ACCEPTA"CE REVIOl 0F FSAR F0 GRAiiD GULF INCLEAR STATIOil i
i Plent !!ame: Grand Culf tiuclear Units 1 a 2 Docket I? umbers: 50-416/417
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Licensing Stage: Acceptance Review titlestone iluater: 22-01 i'aspcasible Cranch: LUR91 and Project l'anager:
C. O. Thoras Requested Coupletion Date: Pay 22, 1978 Review Status: Complete The ts orandum dated fpril 28, 1978 from C. O. Thonas requested evalua-tien of the completeness of the application caterial.of the FSAR for tSe Grand Gulf !!uclear Station Units 1 and 2.
The DSS:PS, Instrur.mta-tioa and Control Systens Branch has reviewed Chapters 1, 7 3 and 7 of the PSAR. The basis used to determine coopleteness of these scctions was the "Standare iomat and Content of Safety Analysis Reports for
- uclear Power Plants" dated Septenbs 1975 (Revision 2) and the Standard Review Plan.
lic have concluded that the applicant has provided mFSAR sufficiently cccplete to proceed with our review. He recorrend that the questions listed under Section 3 of the attached Acceptance Review Report be imediately transt'itted to the applicant.
Inforcation required by respenses to these questions should be included in the FSAR prior to final suhnission for the detailed review.
o.w im a v T. A. I i. /0 T. A. Ippolito, Chief r)
Instrumentation and Control l i s
q Systers Cranch ska of Wsm Safety
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Enclosure:
As Stated
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ACCEPTANCE REVIEW REPORT FOR GPRID GULF NUCLEAR STATION, UNITS 1 & 2 l
1.
Specific Sections Reviewed _
The following sections of the FSAR were reviewed for completeness on the basis of the " Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants", Revision 2, dated Sentember 1975, and the Standard Review Plan.
1.0 2.0 3.10 3.11 7.0 2.
Assessment of Completeness of Areas Reviewed
, The areas reviewed are estimated to be 90% complete.
3.
Identificetion of Deficiencies The following deficiences were noted during the review of the Grand Gulf FSAR. The numbers in the left margin are the ICSB Section number (031) followed by the question number and the FSAR section in paren-thesis.
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Q31.01 Table 3.11-7 of the FSAR shows in several instances that the tempera-(3.11 )
ture profile or maximum temperature is listed as 100 F and in some cases 104 F.
We have a concern if this is intended to indicate the maximum temperature to which the equipment was qualified. Table 2.3-2 indicates that the temperature extreme for the area in which the plant site is located has been as high as 107 F.
Also Table 2.3-7. indicates that temperatures in the area have reached a low of minus 5 F.
There is no reference to the low temperature i
environments in the qualification tables.
g We require that the environmental qualification program for all safety related equipmefit include the complete environmental envelope.
That is both maximum and minimum values expected to occur during plant shutdown, normal operation abnormal operation and during any design basis event and post design basis event.
Provide this information and include any necessary changes in the environmental qualification program of affected equipment.
031.02 We require that the qualifichtion program be provided for at least one
( 3.11) item in each of the following groups of Class lE equipment.
(Both tiSSS supplied and 8.0.P. equipment).
a) Switchgear b) Motor control centers I
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c) Valve operators (in containment) d) Motors e) Logic equipment f) Cables g) Diesel generatcr control equipment h) Sensors i) Limit switches j) Heaters k) Fans I
- 1) Control Boards i
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Instrument racks and panels
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n) Connectors o) Penetrat' ions - including design provisions for the over-
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current protection circuits p) Splices q) Terminal blocks and r) Terminal cabinets The qualification program should include:
a)
Identification of Equipment including,
- 1) Manufacturer
- 2) Manufacturer's type number
- 3) Manufacturer's model number 0
1032 LJ b) Equipment design specification requirements, including,
- 1) The system function requirements
- 2) An environmental envelope which includes all extreme
. parameters, both maximum and minimum values, expected to occur during plant shutdown, normal operation, abnormal operation, and any design basis event.
- 3) Time required to fulfill its function when subjected to any of the extremes of the environmental envelope specified above.
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Test-plan, i
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.I-c d) Test set-up, e) Test procedures, f) Acceptability Goals and requirements, g) Test results h)
Identification of the documents which include and describe the above items i) Justification must be provided when analyses is used to quality equipment.
In accordance with the requirements of Appendix B of 10 CFR 50 the staff requires a statement verifying:
- 1) that all remaining Class lE equipment will be qualified to the program described above and
- 2) that the qualification information will be available for an NRC audit.
l Provide the information requested above.
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of the FSAR states that the RPS (Reactor t
Q31.03 Section 8.3.1.1.5.1 (3.11,7.2 Protection System) power is classified as non-essential, because 8.0)
Also failure of the power supply causes a reactor scram.
(1) the Figure 8.3-11 shows that this RPS power is supplied to RPS, (2) the radiation and neu+.ron monitors and (3) the nuclear steam supply shut off systems.
Since the power supplies to this system are not Class lE we assumed that the voltages and frequencies may exceed or fail I
j below the values used to qualify the safety related equipment i
High and low voltages and low frequencies connected to the bus.
may degrade the safety related equipment to the point when they may not perform their function within the required time frame.
This may be the case even though the failure mode may be for the equipment to return to its deenergized mechanical restored po Equipment will tion and perform its function,when power is removed.
be subjected to high currents as a result of high voltage, low to actuate components.
frequencies and low voltages which fail Describe how the Grand Gulf design prevent this type of degrad to safety related equipment.
Section 7.4.1.4 of the FSAR describes the remote shut down system Q31.04 Describe the features of this design which demonstrate that the s (7.4)
Also, describe the tem satisfies the requirements of GDC 19 and 34.
provisions included in this c:!gn that assure redundant features will not be degraded by a single failure.
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1032 2 Infonnation provided in FSAR section 7.5.2.5.5 indicates that Q31.05 (7.5) the recommendations of Regulatory Guide 1.47 will not be satisfied.
We require that a bypass indication system be crovided for this plant to assure that the operator is aware of the plant status at A commitment to conform to the provisions of Regula-all times.
tory Guide 1.47 during the CP review (included in the CP - SER)
Therefore we require that this final design satisfy was provided.
Prcvide a modified design to include a bypass this commitment.
indication system which satisfies the reconnendations of Regulatory 9
l Guide 1.47.
Describe how this design satisfies position fio. 23 listed in Q31.06
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. Appendix 7A,in the Standard Review Plan._
Section 7.1.2.4 of the FSAR does not indicate conformance to Q31.07 3.11)
Std 323-1971. However, Section 3.11.2.5.1 states that non flSSS (7.1.2.4 supplied equipment purchased before f ovember 1974 has been 323-1971 and equipment qualified in accordance with IEEE Std has been qualified in accordance purchased af ter flovember 1974 with IEEE Std 323-1974.
Correct this inconsistancy.
Section 3.11 of the FSAR does not indicate that the fiSSS Clas Q31.08 (3.11) 1E equipment will satisfy the req 6irements of IEEE-323-1971 nor Identify and justify all exceptions to this the 1974 version.
standard for qualifyi.ng all llSSS supplied Class lE equipment.
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In view of the natural phenomenon (tornado) which recently occurred Q31.09 i
(3.10 )
at your site, identify all portions of the IE equipment that were In addition provide a des-damaged or degraded during this event.
cription which justifies that each of those equipment still satisfy the requirements of the present design and the commissions require-ments identified in Table 7.1 of the Standard Review Plan.
Justify use of RPS inputs from devices mounted on non-seismically.
Q31.10 qualified equipment and/or located in non-seismically qualified (7. 2 )
(7.3 )
Specific examples are turbine trip inputs and generator I
enclosures.
l Also justify use of these inputs for recir-load rejection inputs.
culation pump trip (RPT).
Identify and justify any other trip inputs that may be included in this category.
, Identify and justify all exceptions taken to all branch technical Q31.ll (7) positions listed in appendix 7A of the Standard Review Plan.
Where these positions are discussed in the FSAR, identify all sec-tions where they appear.
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Identify and justify all deviations to the acceptance criteria Q31.12 If this informa-(7) listed on Table 7.1 of the Standard Review Plan.
tion is already included in the FSAR list each section where it is discussed.
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Several previously reviewed BWR installations included a start up Q31.13 (7) transient monitoring system to provide recordings for selected There has i
parameter during the start up and warranty testing.
If been no information in the FSAR which describes this system.
this system or any similar system is intended for use in the Grand Gulf Units provide the following information.
provide separation requirements for all permanently installed 1.
I cables and equipment.
provide separation requirements for all temporary cables 2.
and equipmcat._
Identify all safety related parameters which will be monitored.
3.
Describe the isolation devices, with acceptable qualification, 4.
used to isolate the safety related parameters from the monitoring system.
Describe all other provisions in this design to prevent failures 5.
of this system from degrading all safety related systems.
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