ML19344D566
| ML19344D566 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/07/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Andognini G BOSTON EDISON CO. |
| References | |
| NUDOCS 8004250037 | |
| Download: ML19344D566 (2) | |
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o UNITED STATES
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APRIL 7
1900 Docket No. 50-293 Mr. G. Carl Andognini Boston Edison Company M/C NUCLEAR 800 Boylston Street Boston, Massachusetts 02199
Dear Mr. Andognini:
RE: MODIFICATIONS TO BOILING WATER REACTOR CONTROL R0D DRIVE SYSTEMS Enclosed you will find a copy of our January 28, 1980 letter to General Electric which discusses the NRC staff's conclusions regarding proposed control rod drive (CRD) system modifications related to the elimination of cracking in the CRD return line nozzle. You will also find a copy of our February 11, 1980 letter to GE regarding additional analyses of boil-off rates and CRD system makeup capability. This letter also responds to a GE-proposed draft procedure for optimizing CRD pump flow to the reactor vessel.
We have requested that no modifications be performed on operating reactors until complete guidance has been issued in NUREG-0619. We understand, however, that prior to our request, modifications were performed at your facility under 10 CFR 50.59. NUREG-0619 will provide requirements for your facility. We anticipate issuing NUREG-0619 in its "For Coment" form in April 1980.
If we can be of assistance, please contact your Project Manager.
Sincerely, M.A AD __
d ThomasM.Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Enclosures:
As stated cc w enclosures:
See next page 8004250 d 3 7
Mr. G. Carl Andognini
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000 Boston Edison Company,.
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Mr. Paul J. McGuire Pilgrim Station Acting Manager L
Boston Edison Company RFD #1, Rocky Hill Road Plymouth, Massachusetts 02360 Henry Herrmann, Esquire' Massachusetts Wildlife Federation 151 Tremont Street Boston, Massachusetts 02111 Plymouth Public Library North Street Plymouth, Massachusetts 02360 i
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,I January 28, 1980 t
f Generic Technical Activity A-10 i
t Mr. Richard Gridley, Manager Fuel and Services Licensing General Electric Company 175 Curtner Avenue San Jose, California 95215 l
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Dear Mr. Gricley:
t Since the initial discovery of cracking in boiling water reactor (BVR) j control rod drive return line (CRDRL) nozzles in early 1977, General I
Electric (GE) has proposed a nuncer of solutions to the proolem in the f
course of which several documents were submitted for NRC staff review.
'j These cocuments were as follows:
Letter of March
,1979, G. G. Sherwoo s (GE) to Y. Stello and 1.
R. Ma:: son (NRC) regarcing calculation of CRD system return flow j
capacity; Letter of April 9,1979, G. G. Sherwood (GE) to Y. Stello and 2.
R. Mattson (NRC) forwarding results of CRD system solenoid valve encarance testing; Letter of May 1, 1979, G. G. Sherwood (GE) to Y. Stello and i
3.
R. Mattson (HRC) forwarding results of CRD system solenoid valva performance testing; and l
Letter of Novee:ber 2,1979, G. G. Sherwood (GE) to R. P. Snaider 4
(KRC) forwarcing additional information as requested regarcing CRD hydraulic system performance, especially with regard to corrosion i
procucts e=anating fro: carbon steel pipin3 All concerned the GE rationale for the latest proposed systa= nodification to prevent noz le cracking; namly, total removal of the CRDRL and cutting anc capping of the CRDRL nc::le. Previous submittals had presentec the bases for the other socification proposals discussed herein.
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W A S HINGTO N, D. C. 20555 February 11, 1930 Generic Task fio. A-10 Mr. Richard Gridley, Manager Fuel & Services Licensing General Electric Cecpany 175 Curtner Avenue Sar. Jose, California 95125
Dear Mr. Gridley:
By letter dated tiovember 27, 1979, you forwarded results of analyses of boil-off rates and.Cer. trol Rod Drive (CRD) System ? ump makeup capability for plants not previously addressed in earlier related submittals. The letter also included a draft procedure for optimizing CRD pump flow to the reactor vessel.
The ldvember 27, 1979 letter was not included in the fiRC's Unresolved Safety Issue A-lO review and the analyzed classes of plants will not be included in tiUREG-0519, which resolves A-10 a'nd is tentatively scheduled for issuance in "For Coment" form by February 29, 1980. However, we see no reason why licensees and applicar.ts cannot use the results in the plant-specific analyses (and testing) required by tiUREG-0519.
Significantly more cetail will be recuired in their submittals, however, particularly with regard to the assump-tiens utilized in derivation of the various flow rates.
We concur that the GE-proposed procedure for optimization of CR0 system flow to the pressure vessel provides a necessary first step toward reaching the desired goal.
Hoaever, in our opinion it is too cumbersome with regard to measurement of pump discharge flow. When faced with the need to maintain water level upon loss of other capable high pressure water injection systems, the coerator simply cannot be burdened with the need to refer to pump curves or the need to consider what, if any, other portions of system flow are not included in a respanned flow meter.
We believe that operators should be provided one or tw: meters capable of reliable direct measurement of one and two pump f.lcw.
Sincerely, f.
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Darrell G. Eisenhut, Acting Director Division of Operating Reacters
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