ML19241B393
| ML19241B393 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Rancho Seco  |
| Issue date: | 05/02/1979 |
| From: | Ross D Office of Nuclear Reactor Regulation |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| FOIA-79-98 NUDOCS 7907160361 | |
| Download: ML19241B393 (30) | |
Text
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UNITED STATES 6*
t NUCLEAR REGULATORY COMMISSION
[y5.)1(l j WASHINGTON, D. C. 20555 May 2, 1979 k
/
Note to:
E. Case l
From:
D. Ross, Jr.
Th: persons listed in Enclosure 1 met o 5/1/79 to discuss some proposed changes to the Oconee order. This meetin arose from a desire to consolidate matters expressed do uments (see Bibliography).
The consensus of the meeting or Oconee enclosed.
Based on the sense of the meeti xtrapolated the disposition for Rancho Seco.
k
'f D. Ross, Jr. [
Enclosure:
As stated cc:
H. Denton (w/o encl.)
R. Mattson (w/o encl.)
R. Boyd (w/o encl.)
D. Eisenhut (w/o encl.)
55'<d 37
.4 7 9 0"803GI Ro&_ 77p g
Room Ext.
P. Check 51 6 28030 S. Varga 116 27411 D. Thatcher P-722 27233 A. Oxfurth P-321 27741 F. Rosa P-832 27122 F. Schroeder P-1102 27303 W. Haass P-320D 27741 V. Benaroya P-802B 28057 S. Israel P-ll32D 27591 R. Satterfield P-722 27635 R. McDerrott P-320 27741 D. Beckham 280 27741 R. Reid 328 27381 B. Clayton 280 27741 B. Boger 366 27476 552138
BIBLIOGRA.P,HY 1.
Rancho Seco Feedwater Systems H. B. Clayton & D. Beckham; 4/28/79 2.
Additional Information Applicable to B&W Reactors B. McDermott; 4/24/79 3.
Additional Information Applicable to B&W Reactors B. McDermott; 4/25/79 4.
Additional Information Applicable to B&W Reactors B. McDennott; 4/24/79 5.
Information Applicable to B&W Reactors B. McDermott; 4/23/79 6.
Problems Surfaced in Reviewing Responses to Bulletin 05-A F. J. Williams / 4/24/79 7.
Followup Action Items From B&W Bulletin Review; Memo No.1 D. Eisenhut; 4/25/79 8.
Responses to Bulletins S. Varga; 4/26/79 9.
Draft Letter & Evaluation to SMUD (prepared by Varga, et al.; undated) 10.
Draft Letter & Evaluation to DPC J',.7/}.39 (prepared by Varga, et al.; undated)
' 11.
Letters, DPC to H. Denton a.
April 25, 1979 from W. O. Parker b.
April 25,1979 from W. S. Lee c.
April 25, 1979 from W. O Parker d.
April 25,1979 from W. Owen e.
April 26, 1979 from W. S. Lee 12.
Letter, SMUD to Denton April 27, 1979; by J. J. Matt 13.
Proposed Orders 13a DPC 13b SMUD 14.
Cc aments on Oconee Order by Beckham, Clayton of 4/30/79 15.
Comments on Rancho Seco order by Clayton, Beckham b54140
Recomended Changes to the Order to Duke (0conee) 1.
': a 4 item e - Any additional personnel stationed in the control room should have training in the TMI-2 event. The order specifies this training only for previously licenses SR0's not for current SR0's.
visposition B. Boger, OLB, advises that all licenseu pc-sonnel will recai' 0 NI training prior to standing a watch. Could amend language, but this is style, not substance.
'25'<.'141
2.
Long Tenn Modifications, Item 1 - The additional EFW pumps which are to be installed should also be qualified as Seismic Category I.
The pumps and associated piping should be located in buildings designed to withstand the Safe Shutdown Eartaquake.
Disposition We will consider, when the conceptual design is submitted, the extent to which the new EFW meets the SRP, and justifications for deviations.
To be covered on Long-Tenn Review.
652142 I
3.
Item a, page 1 of letter from Duke Power (Lee) to NRC (Denton) dated April 26,1979 implies that the common EFW header for the three Oconee units will be interconnected. This interconnection should be reviewed imediately to verify that a single failure will not cause loss of EFW flow to one or more units.
Disposition Alreacy considered and found not to be a problem, but will be reconfirmed by the Restart Review.
55Z143
4.
The order should specifically state that, as a long tertn modification, the instrumentation and controls associated with starting all EFW pumps should be safety grade.
Also, the steam generator level control for the EFW system should be independent of the ICS and should be safety grade.
Disposition Long-term review, as per #2.
55214'1
5.
Realignment of EFW from surveillance mode to injection mode should be automatic and accomplished by safety grade equipment.
~
Disposition Long-term review, as per #2.
652145
'OM
fstem capacities are in accordance with the 6.
Verify that the c '"-
assumptions of the accident analysis. Modify the technical specifications to ensure that surveillance testing verifies that the system does not degrade below accident analysis assumptions.
Disposition Restart-review should verify performance (i.e., delivery capability) 55214c
7.
Verify that the final system dysign includes indication of EFW flow to each steam generator in the control room.
Disposition Long-term review, as per #2.
S5'r'b.Y
8 Review and revise, as necessary, the procedures and training for providing alternate sources of water to the suction of the EFW pumps.
Disposition Put in bulletin SER and reconsider in lor.g-tenn review, as per #2.
552148
9.
Design review and modification, as necessary, should be conducted to provide control room annunciation for all auto start conditions of the EFW system.
Disposition Long-term review, as per #2.
552149
9 10.
The EFW system should be modified to provide for automatic switchover to a Seismic Category I water supply on low suction pressure.
Disposition Long-term review, as per #2.
552150
11.
The order should include requirements for the High Pressure Injection System as follows:
a.
System testing to verify that flow has not degraded to less than accident analysis assumptions.
b.
Technical specifications should be modified to require periodic verification of system head and flow for HPI.
c.
The system design should be modified to provide for automatic realignment from the surveillance test mode to the injection mode on an SFAS signal.
Disposition Covered by ASME-XI.
Varga will categorize, send to Eisenhut.
Not a contributor to, or aggravator of, TMI.
5521.T51
12.
All modified systems and their power supplies should be preoperationally tested in accordance with the current revisions to all applicable regulatory guides (e.g., R.G.1.68, Rev. 2, R.G.1.41).
Proposed test abstracts should be submitted to the staff for review.
Disposition Long-tenn review as per #2.
d[327 52
13.
Revisions should be proposed to the plant technical specifications to reflect all design changes and to ensure operability of the affected systems.
Disposition Covered by Bulletin; Varga to put in SER.
Long-term EFW has its own TS.
5521b3
14.
A quality assurance program complying with the requirements of Appendix B to 10 CFR 50 should be applied to all design, procurement, installation, testing, and operation of the proposed changes.
Disposition Long-tern as per #2; put EFW in Appendix B.
- AqQ,
15.
A schedule should be provided by the licensee for implementation of the long tem modifications proposed.
Discosition_
Covered by incorporation of April 25 letter.
L52155
16.
An analysis should be perfonned to ensure that if EFW flow is directed to the lower header in the steam generator, sufficient cooling is maintained in the upper half of the tube bundle to correspond to the minimum heat transfer assumed in the natural circulation analysis.
Disposition Schroeder to remand to AB for analysis.
55Z156 6
Recommended Changes to the Order to SMUD (Rancho Seco')
Comments on Order 1.
Comments on Enclosure 1 to Letter from SMUD to NRC dated April 27, 1979 (Referenced in Item 1 of Order) a)
Item 1 - Starting of auxiliary feedwater pumps should be automatic.
Analysis should ensure that diesels would not be overloaded, that injection by both pumps at design rates will not create undesirable plant transients, and that start signals are initiated by Class lE and Seismic Category I equipment.
Disposition This should be considered in the longer-term review, as proposed on p. 2, para. (9) of SMUD letter of 4/27/79.
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p b)
Item 2 - Realignment of AFW from surveillance mode to injection mode should be automatic and accomplished by safety grade equipment.
Disposition Long-term as per # 1.
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c)
Item 3 - Control of steam generator level by AFW should be accomplished with a safety grade automatic system independent of the ICS. The AFW bypass valve is, a full open/ full shut valve and should not be relied on for system operation except in the event of failure of the safety grade level control system.
Disposition Long term, as per #1.
b5;.3159
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Item 4 - Verification should include system respo'nse time as well as pump capacity.
Disposition Order seems to have time as well as capacity; include in Restart Review.
55g160
e)
Item 5 - Modifications should require indication of AFW flow rate to each steam generator in the control room rather than verification of flow.
Disposition Agree; this should be specifically covered in long-tem review (as per #1).
[
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f)
Ite.n 8 should be changed to ensure that the operator verifies proper response of the AFW system including flows, instead of verifying initiation (i.e., pump running indication).
Disposition This should be covered in long-tem assessment (and be consistent with para, f, regarding flow meters).
5521G'3
2.
The order should include requirements for the High Press,ure Injection system as follows:
a.
System testing to verify that flow has not degraded to less than accident analysis assumptions.
b.
Technical Specifications should be modified to require periodic verification of system head and flow for HPI.
c.
The system design should be modified to provide for automatic realignment from the surveillance test mode to the injection mode on an SFAS signal.
Disposition Covered by ASME-XI. Varga will categorize, send to Eisenhut.
Not a contributor to, or aggravator of TMI.
552163
3.
All modified systems and their power supplies should be preoperationally tested in accordance with the current revisions to all applicable Regulatory Guides (e.g., R.G.1.68, Rev. '2, R.G.1.41).
Proposed test abstracts should be submitted to the staff for review.
Disposition Long-tem review as per #1.
~
e e
4.
Revisions should be proposed to the plant technical specifications to reflect all design changes and to ensure operability of the affected systems.
Disposition Covered by Bulletin; Varga to put in SER.
N e
e 5.
A quality assurance program complying with the requirenEnts of Appendix B to 10 CFR 50 should be applied to all design, procurement, installation, testing, and operation of the proposed changes.
Disposition Long-term as per #1.
.