ML18094B213
| ML18094B213 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/13/1989 |
| From: | Preston B Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-89-21, NLR-N89237, NUDOCS 8912280255 | |
| Download: ML18094B213 (7) | |
Text
PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department DEC 1 S 1989 NLR-N89237 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. c. 20555 Gentlemen:
STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUE REQUIREMENTS NRC GENERIC LETTER 89-21 SALEM GENERATING STATION DOCKET NO. 50-272 AND 50-311 On November 30, 1989, Public Service Electric and Gas Company (PSE&G) submitted a response to your October 19, 1989 letter requesting information concerning the implementation status of Unresolved Safety Issue (USI) requirements.
Based on conversations with Mr. J. Stone, the NRR Project Manager for Salem Generating station, we are revising our submittal to more clearly indicate the actual completion dates for each identified USI.
The actual completion date is shown in parenthesis in the status column of the enclosed Table 1 and reflects the overall completion date for all activities associated with a USI.
Please contact us if you have any questions regarding this transmittal.
~y, B. A. ~n Manager - Licensing & Regulation Enclosures The Energy People f) ()/~
1 Ir 8912280255 891213-------~,
- ADOCK 05000272 p
PNU 95-2168 (40M) 6-89
Document Control Desk NLR-N89237 C
Mr. J. c. Stone 2
Licensing Project Manager -
Salem Ms. K. Halvey Gibson Senior Resident Inspector -
Salem Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief
\\DEC 1 3 1989 New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
USI NO.
A-1 A-2 A-3 A-4 A-5 A-6 A-7 Table 1 STATUS OF UNRESOLVED SAFETY ISSUES FOR SALEM TITLE APPLICABILITY STATUS Water Hammer Asymmetric Loads on RCS Steam Generator Tube Integrity (Westinghouse)
Steam Generator Tube Integrity (CE)
Steam Generator Tube Integrity (B&W)
Mark I Contain.
Short-Term Prog.
Mark I Contain.
Long-Term Prog.
Yes C
Yes Yes No No No No (9/85) c Unit 2 (4/80)
Unit 1 (11/86) c (6/85)
NA NA NA NA Page 1 of 5 REMARKS SER Supp.4 Sect. 10.4, Amend. 37 PS Ltr.6/9/78 Feedwater Test 7/7/80 Original 6/4/81 revised TMI item I.A.2.3, Training Prog.
Accreditation.
Complete 1985 SER Supp.4 Sect. 3. 9.1 4/18/80 for Unit 2.
NRC Ltr.
11/24/86 for Unit 1.
PS Ltr.6/17/85
e e
Table 1 A-8 Mark II Contain.
No NA Pool Dynamic Loads A-9 ATWS Yes c
Unit 1(1EC2173)
(5/89) 7th Outage 10/87-2/88 Unit 2(2EC2174) 4th Outage 8/88-12/88 Human Factors Review (ELE-89-0109)
Comp. 5/3/89 A-10 BWR Feedwater No NA.
Nozzle Cracking A-11 Reactor Vessel Yes NC No action req.
Material unless fracture Toughness toughness level predicted < 50 Ft-Lb.
A-12 Fracture Toughness Yes c
NRC Ltr.1/21/81 of Steam Generator Unit 1 ( 1/81)
SER for Unit 1.
and Reactor Coolant Unit 2 (12/78)
Pump Supports NRC SER Supp.2 Sect. 3.9.4 &
SER Supp. 3 Sect. 3.9.4.
A-17 Sys. Interactions Yes E
Reviewing with (7/93)
Page 2 of 5
Table 1 A-24 Qualification of Yes c
NRC SER Unit 1 Class IE Safety Unit 1 (4/86) 12/5/84 Related Equip.
Unit 2 (5/86)
NRC SER Unit 2 1/14/85 PS Ltr. 2/19/85 NRC Inspection Nos.
50-272/86-23; 50-311/86-23 11/13/86 NRC ltr.
10/19/88, EQ Enforcement Conference A-26 Reactor Vessel Yes c
NRC SER Supp.3 Pressure Unit 1 (2/80)
Sect. 5.2.3.1 Transient Prot.
Unit 2 ( 5/81) installation of Pressurizer Overpressure Prot. (POPS)
Unit 2.
Unit 1 POPS installation.
Amend. 24 TS 2/21/80.
A-31 RHR Shutdown Yes c
Unit 2 only.
Requirements
( 4/81)
NRC SER Supp.3 Sect. 5.7.
Startup testing natural circ.
test report 4/28/81 A-36 Control of Yes c
Phase I -
NRC Heavy Loads
( 11/89)
Acceptance Near Spent 6/22/84 Fuel Phase II -
NRC Closure 6/28/85 Page 3 of 5
Table 1 A-39 Determination of No NA SRV Pool Dynamic Loads and Pressure Transients A-40 Seismic Design Yes E
Evaluating with Criteria (7 /93)
IPE Process for External Events A-42 Pipe Cracks in No NA Boiling Water Reactors A-43 Containment Sump Yes c
NRC SER Supp.5 Performance (10/84)
Sect. 6.3.3.7 Unit 2.
No docum. for Unit 1, but similar design.
A-44 Station Blackout Yes I
PS Ltr. 4/17/89 (See remarks Item 1-0ngoing for antici-Item 2-10/90 pated complet. Item 3-Complete date)
Item 4-NA Item 5-Complete Item 6-Will be comp. within 2 yrs. of NRR notification IAW 10CFR50.63 (c) (3)
A-45 Shutdown Decay Yes E
Incorporated Heat Removal (7/93) into IPE effort Requirements A-46 Seismic Qual.
Yes I
PS Ltr. 8/7/89 of Equipment (See remarks Walkdowns to be in Operating for antici-comp. within 2 Plants pated complet. outages of NRC date) approval.
Tentative dates Unit 1-1/30/92 Unit 2-6/30/91 Integrated with IPE external events.
Page 4 of 5
A-47 A-48 A-49 Table 1 Safety Implication Yes of Control Systems Hydrogen Control Yes
& Effects of Hydrogen Burns on Safety-Related Pressurized Yes Thermal Shock E
NA I
(Continuing reevaluation)
Page 5 of 5 Response to GL 89-19 due 3/90.
NA for large, dry,PWRs.
PS Ltr. 1/4/80 NRC SER 3/21/81 Supp. 4 4/24/81 Generic Issue 121 tracking.
Comp. prelim.
RTpts screening via Reg.Guide
- 1. 99 Rev. 2.
Will not reach till after license exp.
PS Ltr.11/17/88 Periodic reeval to compare with predicted value Submitted LCR 88-14 for PT curves,awaiting approval.