ML19095A054
| ML19095A054 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/16/1977 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Case E, Reid R Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19095A054 (1) | |
Text
e RICHMOND,VIRGIN:IA. 23261 cy May 16, 1977 Mr. Eds
- *\\:ase,. _Acting Director Office of Nuclear Reactor.Re.g'ulation Attention:
Mr. Robert w. Reid, Chief Serial No.*.184..
LQA/DWSjr:krb Docket Nos.. 50~2so Operating Reactors Branch No.* 4 Division of Oper.ating Reactors
- u. S. Nuclear Regulatory Commission Washington, D. C.
20555
. 50-281 License Nos. DPR~32 DPR-37
Dear Mr. Case*:
On September. 21, _1,973, the Commission approved station modifi-cations to mitigate the consequences* of certain postulated high energy line ruptures.* Since that time; _the modified systems have been in-stalled and successfully operated. *Furthermore, during this period of time, these systems have. beeri operated and tested by procedures commensurate with those *of other safety systems.
It is for this reason that your staff may want to consider a formal upgrading of administrative control in the form of te.chriical specif.ications.
There-fore, enclosed are the proposed specif.ication changes and the basis for these changes.
A de.scripti.on and drawing of the modified systems is also enclosed.
The proposed specif.ications for. the RWST. cross-connect will require the operability of the cross-connect line whenever a reactor is critical.
In addition,. the amount of. borated water in the Unit 2 Refueling Water Storage Tank will be.come a limiting condition for operation for Unit 1* and vice_:versa.
The. *proposed specifications for the auxiliary.feedwater cross-connect and associated tanks and pumps will require operability. before increasing above. 3S0°F and 450 psig.
- In addition, _the amount of water in the Unit 2 condensate storage tank will become a 1*imiting. condition for operation for Unit 1 and vice-versa.
Thes*e changes. have been reviewed by both Station and System Nuclear Safety and Operating Committees.
Further.,. _it has been.deter-mined that thes*e changes do not involve: an unreviewed safety question as-defined in 10 CFR. 50.*.59.
Attachments:
- 1.
System Description
- 2.
Proposed Specifications cc:
Mr. Norman C. MoseTey Very truly yours,
--,?'.
- ! ~>,'.. * :_:_.. -*.
C. M. Stallings Vice President-Power Supply and Production Operations 771400074